High Temperature Reactor With Reduced Silo Height
US-2025087378-A1 · Mar 13, 2025 · US
US2024404715A1 · US · A1
| Field | Value |
|---|---|
| Publication number | US-2024404715-A1 |
| Application number | US-202418663145-A |
| Country | US |
| Kind code | A1 |
| Filing date | May 14, 2024 |
| Priority date | May 30, 2023 |
| Publication date | Dec 5, 2024 |
| Grant date | — |
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A fuel assembly includes: a square cylinder channel box having a square cross-section; and fuel rods disposed in a square lattice shape and filled with a nuclear fuel material. The fuel rods includes: a first rod disposed in an outer layer in the box and a second rod disposed in an inner layer in the box and having a larger diameter than the first rod. An absolute value of a difference between a hydraulic equivalent diameter around the first rod and a hydraulic equivalent diameter between a surface in the box and the first rod is more than or equal to a value obtained by multiplying an absolute value of a difference between the hydraulic equivalent diameter around the first rod and the hydraulic equivalent diameter around the second rod by a ratio of a cross-sectional area of the inner layer to a cross-sectional area of the entire box.
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What is claimed is: 1 . A fuel assembly comprising: a channel box that is a square cylinder having a square cross section, and a plurality of fuel rods disposed in a square lattice shape in the channel box, and filled with a nuclear fuel material inside, the plurality of fuel rods including: a first fuel rod disposed in an outer layer portion in the channel box; and a second fuel rod that is disposed in an inner layer portion in the channel box and has a diameter larger than the first fuel rod, wherein an absolute value of a difference between a hydraulic equivalent diameter around the first fuel rod and a hydraulic equivalent diameter between a wall surface in the channel box and the first fuel rod is more than or equal to a value obtained by multiplying an absolute value of a difference between the hydraulic equivalent diameter around the first fuel rod and a hydraulic equivalent diameter around the second fuel rod by a ratio of a cross-sectional area of the inner layer portion of the channel box to a cross-sectional area of the entire channel box. 2 . The fuel assembly according to claim 1 , wherein a volume of a nuclear fuel material disposed in the fuel assembly is equal to or larger than a volume of a nuclear fuel material when the first fuel rods are disposed in a square lattice shape in the channel box. 3 . The fuel assembly according to claim 1 , wherein a third fuel rod having a larger diameter than the second fuel rod is disposed in a further inner layer of a region in which the second fuel rod is disposed, and an absolute value of a difference between a hydraulic equivalent diameter around the second fuel rod and a hydraulic equivalent diameter between the first fuel rod and the second fuel rod is more than or equal to a value obtained by multiplying an absolute value of a difference between a hydraulic equivalent diameter around the third fuel rod and a hydraulic equivalent diameter around the second fuel rod by a ratio of a flow path area of a region in which the third fuel rod is disposed to a flow path area of a region in which the second fuel rod and the third fuel rod are disposed. 4 . The fuel assembly according to claim 1 , wherein the first fuel rods are disposed in 12 rows and 12 columns in the channel box. 5 . The fuel assembly according to claim 1 , wherein a lower end portion is supported by a lower fuel support member, an upper end portion is supported by an upper fuel support member, a fuel spacer that bundles the plurality of fuel rods is held, and a support rod without containing a fuel material is disposed at each of four corners of an outermost peripheral region of a fuel rod disposition in a cross section of the fuel assembly. 6 . A nuclear reactor core, wherein a plurality of the fuel assemblies according to claim 1 are loaded.
comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods · CPC title
Shape of its constituent parts · CPC title
Relative disposition of the elements in the bundle lattice · CPC title
Supports for spacer grids · CPC title
Nuclear fission reactors · CPC title
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