Managing nuclear reactor spent fuel rods
First Claim
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1. A spent nuclear fuel rod canister, comprising:
- a submersible pressure vessel comprising a casing that defines an 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 that defines a fluid pathway between a top portion of the interior cavity and a bottom portion of the interior cavity;
an annulus defined between the riser and the casing; and
a heat exchanger attached to the casing of the pressure vessel,the heat exchanger comprising at least one conduit that is at least partially disposed exterior to the casing,the at least one conduit comprising an interior volume flowpath that is in fluid communication with the interior cavity of the pressure vessel,the at least one conduit comprisinga first conduit comprising an end of the interior volume flowpath that includes an opening located in the riser anda second conduit comprising an end of the interior volume flowpath that includes an opening located in the annulus.
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Abstract
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 and a rack enclosed within the interior cavity and configured to support one or more spent nuclear fuel rods. The spent nuclear fuel rod canister includes a heat exchanger attached to the casing of the pressure vessel.
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Citations
20 Claims
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1. A spent nuclear fuel rod canister, comprising:
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a submersible pressure vessel comprising a casing that defines an 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 that defines a fluid pathway between a top portion of the interior cavity and a bottom portion of the interior cavity; an annulus defined between the riser and the casing; and a heat exchanger attached to the casing of the pressure vessel, the heat exchanger comprising at least one conduit that is at least partially disposed exterior to the casing, the at least one conduit comprising an interior volume flowpath that is in fluid communication with the interior cavity of the pressure vessel, the at least one conduit comprising a first conduit comprising an end of the interior volume flowpath that includes an opening located in the riser and a second conduit comprising an end of the interior volume flowpath that includes an opening located in the annulus. - View Dependent Claims (2, 3, 4, 5, 6, 7, 8, 9, 10)
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11. A method of dissipating decay heat generated by a spent nuclear fuel rod, the method comprising:
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loading at least one spent nuclear fuel rod into a rack positioned within an interior cavity of a spent nuclear fuel rod canister, the canister comprising; a submersible pressure vessel comprising a casing that defines an interior cavity that is at least partially filled with a fluid coolant, 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, and a heat exchanger attached to the casing of the pressure vessel, the heat exchanger comprising at least one conduit that is at least partially disposed exterior to the casing, the at least one conduit comprising an interior volume flowpath that is in fluid communication with the interior cavity of the pressure vessel, the at least one conduit comprising a first conduit comprising an end of the interior volume flowpath that includes an opening located in a riser that defines a fluid pathway between a top portion of the interior cavity and a bottom portion of the interior cavity and a second conduit comprising an end of the interior volume flowpath that includes an opening located in an annulus defined between the riser and the casing; submerging the spent nuclear fuel rod canister in a heat transfer fluid contained in a spent fuel pool; transferring decay heat from the spent nuclear fuel rod to the fluid coolant; circulating the heated fluid coolant through the riser and into the end of the first conduit; transferring the decay heat from the heated fluid coolant, through the casing, and to the heat transfer fluid in the spent fuel pool; and circulating the fluid coolant from the end of the second conduit to and through the annulus. - View Dependent Claims (12, 13, 14, 15, 16, 17, 18, 19, 20)
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Specification