Automatically adjusting seismic restraint system for nuclear fuel storage
US-2024387066-A1 · Nov 21, 2024 · US
US9406409B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9406409-B2 |
| Application number | US-201313786643-A |
| Country | US |
| Kind code | B2 |
| Filing date | Mar 6, 2013 |
| Priority date | Mar 6, 2013 |
| Publication date | Aug 2, 2016 |
| Grant date | Aug 2, 2016 |
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A spent nuclear fuel rod canister includes a submersible pressure vessel including a casing that defines an interior cavity, the casing including a corrosion resistant and heat conductive material with a thermal conductivity of above about 7.0 watts per meter per kelvin; and a rack enclosed within the interior cavity and configured to support one or more spent nuclear fuel rods.
Opening claim text (preview).
What is claimed is: 1. A spent nuclear fuel rod canister, comprising: a submersible pressure vessel comprising a casing that defines a hermetically sealed interior cavity, the casing comprising a corrosion resistant and heat conductive material; a rack enclosed within the interior cavity and configured to support one or more spent nuclear fuel rods; a riser having a first fluid pathway through the riser between a top portion of the interior cavity and a bottom portion of the interior cavity, the rack being positioned within the first fluid pathway of the riser; and an open annulus defined between the riser and the casing, the open annulus surrounding the riser and the rack to define a second fluid pathway, the second fluid pathway being fluidly coupled to the first fluid pathway, each of the first fluid pathway and the second fluid pathway being enclosed within the sealed interior cavity of the casing. 2. The spent nuclear fuel rod canister of claim 1 , further comprising a first hemispherical enclosure coupled to the casing at a top end of the casing, the first hemispherical enclosure comprising a radiussed interior surface that defines a top portion of the interior cavity. 3. The spent nuclear fuel rod canister of claim 2 , further comprising a second hemispherical enclosure coupled to the casing at a bottom end of the casing, the second hemispherical enclosure comprising a radiussed interior surface that defines a bottom portion of the interior cavity. 4. The spent nuclear fuel rod canister of claim 1 , further comprising a fuel basket positioned in the interior cavity within the riser and near the bottom portion of the interior cavity. 5. The spent nuclear fuel rod canister of claim 4 , wherein the fuel basket comprises: a perforated support plate adjacent a bottom surface of the rack, the first fluid pathway fluidly coupled to the bottom portion of the interior cavity through the perforated support plate. 6. The spent nuclear fuel rod canister of claim 1 , further comprising a heat exchanger attached to the casing of the pressure vessel. 7. The spent nuclear fuel rod canister of claim 6 , wherein the heat exchanger comprises at least one conduit that is at least partially disposed exterior to the casing and is in fluid communication with the interior cavity. 8. The spent nuclear fuel rod canister of claim 1 , wherein the corrosion resistant material comprises a radioactivity conduction material.
Arrangements for preventing occurrence of critical conditions, e.g. during storage · CPC title
Heat-removal systems, e.g. using circulating fluid or cooling fins · CPC title
Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom (disposal of waste material G21F9/00) · CPC title
Storage racks; Storage pools · CPC title
Containers for fuel elements · CPC title
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