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US 12,094,618 B2Granted
Nuclear reactor fuel assemblies and process for production
AssigneeBWXT Advanced Technologies LLC
InventorsScott J. Shargots, Gary W. Neeley, Ryan Z. Ziegler
Life of this patent
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Abstract
A nuclear fuel assembly for a nuclear reactor core including at least one fuel cartridge having a lattice structure including an outer wall defining an interior volume, at least one flow channel extending through the interior volume of the lattice structure, at least one lattice site disposed in the interior of the lattice structure; and at least one fuel compact disposed within a corresponding one of the at least one lattice site. A cross-sectional shape of the at least one fuel compact is the same as a cross-sectional shape of the corresponding one of the at least one lattice site.
Claims20
A nuclear fuel assembly for a nuclear reactor core, comprising:
- at least one fuel cartridge comprising:
- a lattice structure including an outer wall defining an interior volume and a plurality of inner walls, the lattice structure defining a longitudinal center axis,
- at least one elongated tube extending through the interior volume of the lattice structure to define a flow channel;
- the lattice structure defining at least one lattice site disposed in the interior of the lattice structure adjacent to the elongated tube, a horizontal cross-sectional shape of the lattice site being defined at least in part by at least one of the inner walls and a corresponding portion of an outer circumference of the elongated tube;
- and
- at least one fuel compact disposed within a corresponding one of the at least one lattice site, the fuel compact including a fuel compact cladding tube defining an interior volume,
- wherein a horizontal cross-sectional shape of the at least one fuel compact is non- circular and is the same as the horizontal cross-sectional shape of the corresponding one of the at least one lattice site.
4 more elements
A nuclear fuel assembly for a nuclear reactor core, comprising:
- at least one fuel cartridge comprising:
- a lattice structure including an outer wall defining an interior volume;
- at least one flow channel extending through the interior volume of the lattice structure;
- at least one lattice site disposed in the interior of the lattice structure;
- and
- at least one fuel compact including a longitudinal center axis, comprising:
- a fuel compact cladding tube defining an interior volume, and
- a plurality of fuel pins arranged inside the fuel compact cladding in parallel with one another, each fuel pin including a longitudinal center axis, a pin cladding tube defining an interior volume, and fissionable fuel disposed within the interior volume of the pin cladding tube,
- wherein the plurality of fuel pins include at least a first fuel pin having an outer diameter that is greater than an outer diameter of a second fuel pin, and the plurality of fuel pins is disposed within the interior volume of the fuel compact cladding tube so that a first distance between the longitudinal center axis of the first fuel compact fuel pin and the longitudinal center axis of the fuel compact is greater than a second distance between the longitudinal center axis of the fuel compact second fuel pin and the longitudinal center axis of the fuel compact.
6 more elements
A nuclear fuel assembly for a nuclear reactor core, comprising:
- at least one fuel cartridge comprising:
- a lattice structure including an outer wall defining an interior volume, the lattice structure defining a longitudinal center axis;
- a plurality of elongated tubes extending through the interior volume of the lattice structure to define respective flow channels;
- the lattice structure defining a plurality of lattice sites disposed in the interior of the lattice structure;
- and
- a plurality of fuel compacts disposed within corresponding ones of the lattice sites,
- wherein a horizontal cross-sectional shape of each of the fuel compacts is non-circular and is the same as a horizontal cross-sectional shape of the corresponding lattice site and wherein a portion of the horizontal cross-sectional shape of the corresponding lattice site is defined by a corresponding portion of an outer circumference of an adjacent elongated tube,
- wherein each fuel compact includes:
- a fuel compact cladding tube defining an interior volume, and
- a plurality of fuel pins, each fuel pin including a pin cladding tube defining an interior volume, and fissionable fuel disposed within the interior volume of the pin cladding tube,
- wherein the plurality of fuel pins is disposed within the interior volume of the fuel compact cladding tube, and the horizontal cross-sectional shape of the fuel compact is defined by the fuel compact cladding tube.
8 more elements
Dependencies are inferred from the claim text.