Rib-type roughness design for improved heat transfer in PWR rod bundles

Patent metadata

Field	Value
Publication number	US-9514851-B2
Application number	US-201314064531-A
Country	US
Kind code	B2
Filing date	Oct 28, 2013
Priority date	Mar 12, 2013
Publication date	Dec 6, 2016
Grant date	Dec 6, 2016

Abstract

The invention pertains to a nuclear fuel rod for a nuclear reactor. The fuel rod has a cladding. The cladding's external surface has a surface texture that includes a rib. The rib coils around the circumference of the cladding. The rib length forms a sequence of continuous rib loops uniformly spaced along an axial length of the cladding. The ratio of rib height to cladding diameter is greater than or equal to 0.0134 and less than or equal to 0.0268. The ratio of rib height to rib width is greater than or equal to 0.8 and less than or equal to 1.2. A pitch measured between adjacent rib loops is greater than or equal to 9× rib height and less than or equal to 12× rib height. The rib enhances fuel rod heat transfer in a region downstream of grid mixing vanes, where turbulence is dissipated.

First claim

What is claimed is:

1. A fuel rod having first and second closed ends, encapsulating a fissionable material axially along at least a portion of an interior volume thereof, and an exterior of the fuel rod comprising a cladding that extends substantially axially between the first and second closed ends, the cladding comprising:
an external surface;
a circumference;
an axial length;
a diameter; and
a surface modification applied to at least a portion of the external surface, the surface modification comprising:
a rib having a length, a height and a width, the length of the rib coils around the circumference of the external surface of the cladding;
a sequence of continuous rib loops uniformly spaced along the axial length of the cladding formed by the length of the rib; and
a pitch measured between adjacent rib loops in the sequence of continuous rib loops,

wherein a ratio of the height of the rib to the diameter of the cladding is greater than or equal to about 0.0134 and less than or equal to about 0.0268,
wherein a ratio of the height of the rib to the width of the rib is greater than or equal to about 0.8 and less than or equal to about 1.2, and
wherein the pitch is greater than or equal to about nine times the height of the rib and less than or equal to about 12 times the height of the rib.

2. The fuel rod of claim 1 , wherein each rib loop in the sequence of continuous rib loops is offset from a horizontal axis by an angle ranging from about 0 degrees to about 45 degrees.

3. The fuel rod of claim 1 , wherein the surface modification is applied to only a portion of the external surface of the cladding.

4. A nuclear fuel assembly, comprising:
a spaced array of a plurality of axially extending elongated tubular pressurized water reactor nuclear fuel elements, each having first and second closed ends, encapsulating a fissionable material axially along at least a portion of an interior volume thereof, and an exterior of at least one of the fuel elements comprising a cladding that extends substantially axially between the first and second closed ends, the cladding comprising:
an external surface;
a circumference;
an axial length;
a diameter; and
a surface texture varying axially in a prescribed pattern along at least a portion of an axial length of the external surface of said cladding, the surface texture, comprising:
a rib having a length, a height and a width, the length of the rib coils around the circumference of the external surface of the cladding;
a sequence of continuous rib loops uniformly spaced along the axial length of the cladding formed by the length of the rib; and
a pitch measured between adjacent rib loops in the sequence of continuous rib loops,

wherein a ratio of the height of the rib to the diameter of the cladding is greater than or equal to about 0.0134 and less than or equal to about 0.0268,
wherein a ratio of the height of the rib to the width of the rib is greater than or equal to about 0.8 and less than or equal to about 1.2, and
wherein the pitch is greater than or equal to about nine times the height of the rib and less than or equal to about 12 times the height of the rib.

5. The nuclear fuel assembly of claim 4 , wherein a plurality of axially spaced spacer grids surround and affix the fuel elements in the spaced array and wherein said surface texture of the cladding is located in a span between a consecutive pair of the spacer grids.

6. A method of enhancing heat transfer in a nuclear fuel core containing a plurality of fuel rods having first and second closed ends, encapsulating a fissionable material axially along at least a portion of an interior volume thereof, and an exterior of at least one of the fuel rods comprising a cladding having a diameter and an external surface that extends substantially axially between the first and second closed ends, comprising:
modifying the external surface of the cladding for at least a portion of the plurality of fuel rods; and
applying to at least a portion of the external surface to be modified a roughness, comprising:
a rib having a length, a height and a width, the length of the rib coils around a circumference of the external surface of the cladding;
a sequence of continuous rib loops uniformly spaced along the axial length of the cladding formed by the length of the rib; and
a pitch measured between adjacent rib loops in the sequence of continuous rib loops,

wherein a ratio of the height of the rib to the diameter of the cladding is greater than or equal to about 0.0134 and less than or equal to about 0.0268,
wherein a ratio of the height of the rib to the width of the rib is greater than or equal to about 0.8 and less than or equal to about 1.2, and
wherein the pitch is greater than or equal to about nine times the height of the rib and less than or equal to about 12 times the height of the rib.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Carrilho Leo A
• Dzodzo Milorad B

Classifications

• G21C3/08 Primary

  provided with external means to promote heat-transfer, e.g. fins, baffles · CPC title

• G21C3/322

  Means to influence the coolant flow through or around the bundles · CPC title

• Y02E30/40

  Cross-Sectional Technologies · mapped topic

• Y02E30/30

  Nuclear fission reactors · CPC title