Managing nuclear reactor spent fuel rods

Patent metadata

Field	Value
Publication number	US-10453578-B2
Application number	US-201615083543-A
Country	US
Kind code	B2
Filing date	Mar 29, 2016
Priority date	Mar 6, 2013
Publication date	Oct 22, 2019
Grant date	Oct 22, 2019

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.

First claim

What is claimed is:

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 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.

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; and
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.

3. 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.

4. The spent nuclear fuel rod canister of claim 3 , wherein the fuel basket comprises:
a perforated support plate adjacent a bottom surface of the rack, the fluid pathway fluidly coupled to the bottom portion of the interior cavity through the perforated support plate.

5. The spent nuclear fuel rod canister of claim 1 , wherein the at least one conduit further comprises a third conduit comprising another end of the interior volume flowpath that includes an opening located in the annulus.

6. The spent nuclear fuel rod canister of claim 1 , wherein the casing is configured to permit radiation from the one or more spent nuclear fuel rods therethrough.

7. The spent nuclear fuel rod canister of claim 2 , wherein the end of the first conduit is positioned below a liquid level of a coolant that at least partially fills the interior cavity of the casing.

8. The spent nuclear fuel rod canister of claim 7 , further comprising a fuel basket positioned in the interior cavity within the riser and near the bottom portion of the interior cavity.

9. The spent nuclear fuel rod canister of claim 8 , wherein the fuel basket comprises:
a perforated support plate adjacent a bottom surface of the rack, the fluid pathway fluidly coupled to the bottom portion of the interior cavity through the perforated support plate.

10. The spent nuclear fuel rod canister of claim 9 , wherein the at least one conduit further comprises a third conduit comprising another end of the interior volume flowpath that includes an opening located in the annulus.

11. A method of dissipating decay heat generated by a spent nuclear fuel rod, the method comprising:
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.

12. The method of claim 11 , wherein the fluid coolant is circulated through natural circulation.

13. The method of claim 11 , further comprising exposing the casing of the spent fuel canister to ambient air.

14. The method of claim 13 , further comprising:
based on the exposure to ambient air, phase changing a portion of the fluid coolant from a liquid to a gas in the spent nuclear fuel rod canister; and
phase changing the gas back to a liquid condensate on an interior surface of the casing based at least in part on heat transfer between the gas and the ambient air.

15. The method of claim 11 , wherein transferring the decay heat from the heated fluid coolant, through the casing, and to the heat transfer fluid in the spent fuel pool comprises:
convectively transferring the decay heat from the heated fluid coolant to the casing; and
convectively transferring the decay heat from the casing to the heat transfer fluid.

16. The method of claim 11 , wherein a rate at which heat is transferred from the spent fuel rod is at least as great as a rate at which the spent nuclear fuel rod produces decay heat.

17. The method of claim 11 , wherein the casing is configured to permit radiation from the at least one spent nuclear fuel rod therethrough.

18. The method of claim 11 , wherein the at least one conduit further comprises a third conduit comprising another end of the interior volume flowpath that includes an opening located in the annulus.

19. The method of claim 18 , further comprising circulating the fluid coolant from the end of the third conduit to and through the annulus.

20. The method of claim 19 , wherein the fluid coolant is simultaneously circulated from the ends of the second and third conduits to the annulus.

Assignees

• Nuscale Power Llc

Inventors

• Reyes Jr Jose N
• Colbert Christopher

Classifications

• G21C19/40

  Arrangements for preventing occurrence of critical conditions, e.g. during storage · CPC title

• G21F5/012 Primary

  Fuel element racks in the containers · CPC title

• G21C19/08

  Means for heating fuel elements before introduction into the core; Means for heating or cooling fuel elements after removal from the core · CPC title

• G21F5/008

  Containers for fuel elements · CPC title

• G21C19/32

  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