Nuclear reactors including heat exchangers and heat pipes extending from a core of the nuclear reactor into the heat exchanger and related methods

Patent metadata

Field	Value
Publication number	US-10910116-B2
Application number	US-201715461173-A
Country	US
Kind code	B2
Filing date	Mar 16, 2017
Priority date	Mar 16, 2017
Publication date	Feb 2, 2021
Grant date	Feb 2, 2021

Abstract

A nuclear reactor including a reactor core comprising a plurality of fuel materials and a plurality of heat pipes. The nuclear reactor further includes a heat exchanger coupled to the reactor core defining a flow path in an open volume including at least two heat pipes of the plurality of heat pipes. Methods of operating a nuclear reactor include passing fluid through an open volume in a heat exchanger including at least two heat pipes extending from a reactor core.

First claim

What is claimed is:

1. A nuclear reactor, comprising:
a reactor core comprising
a plurality of fuel materials and a plurality of heat pipes interspersed with
the plurality of fuel materials,
each heat pipe of the plurality of heat pipes being partially positioned and configured to transfer energy from at least one fuel material of the plurality of fuel materials; and

a first heat exchanger and a second heat exchanger, wherein
the first heat exchanger and the second heat exchanger are coupled to the reactor core at opposing ends,
each of the first heat exchanger and the second heat exchanger comprising at least one inlet and at least one outlet,

the plurality of heat pipes extending from the reactor core into the first heat exchanger and the second heat exchanger,
each of the first heat exchanger and the second heat exchanger defining an open flow path extending between the at least one inlet and the at least one outlet that intersects each heat pipe of the plurality of heat pipes
such that fluid traveling along the open flow path flows substantially freely between the plurality of heat pipes through substantially all of the open flow path and intersects and directly contacts each heat pipe of the plurality of heat pipes,
the fluid able to travel substantially undivided along the open flow path along substantially an entire length of each heat pipe of the plurality of heat pipes within the first heat exchanger and the second heat exchanger and,
at least some of the heat pipes of the plurality of heat pipes configured to be contacted by the fluid more than once,

each of the first heat exchanger and the second heat exchanger being configured to transfer energy from heat transfer fluid in the plurality of heat pipes directly to the fluid traveling along the open flow path
to condense the heat transfer fluid in the plurality of heat pipes and form a liquid able to travel within each heat pipe of the plurality of heat pipes to the reactor core.

2. The nuclear reactor of claim 1 , wherein the plurality of fuel materials comprises a plurality of fuel rods.

3. The nuclear reactor of claim 1 , wherein at least one of the first heat exchanger and the second heat exchanger comprises a plurality of baffles.

4. The nuclear reactor of claim 3 , wherein the plurality of baffles defines an at least partially tortuous flow path between the at least one inlet and at least one outlet.

5. The nuclear reactor of claim 3 , wherein the plurality of baffles defines a spiral flow path between the at least one inlet and at least one outlet.

6. The nuclear reactor of claim 1 , wherein the plurality of fuel materials and the plurality of heat pipes extend through a majority of the reactor core.

7. The nuclear reactor of claim 6 , wherein each heat pipe of the plurality of heat pipes lacks an exterior sleeve.

8. The nuclear reactor of claim 1 , wherein each of the plurality of heat pipes comprises a closed structure having closed ends and containing the heat transfer fluid.

9. The nuclear reactor of claim 1 , wherein at least some of the plurality of heat pipes extend from the first heat exchanger through the reactor core and into the second heat exchanger.

10. A method of operating the nuclear reactor of claim 1 , the method comprising:
transferring energy from a nuclear fuel material to each heat pipe of the plurality of heat pipes of the reactor core;
at least partially changing the heat transfer fluid within each heat pipe of the plurality of heat pipes from a liquid state to a gaseous state in response to the transferring of the energy;
moving the heat transfer fluid in the gaseous state along a length of each heat pipe of the plurality of heat pipes from the reactor core to the first heat exchanger and the second heat exchanger; and
passing the fluid through an open volume defined by the open flow path in the first heat exchanger and the second heat exchanger to transfer at least a portion of the energy from the heat transfer fluid in the gaseous state to the fluid.

11. The method of claim 10 , further comprising returning the heat transfer fluid within each heat pipe of the plurality of heat pipes from the gaseous state to the liquid state in the first heat exchanger and the second heat exchanger responsive to passing the fluid through the open volume in the first heat exchanger and the second heat exchanger.

12. The method of claim 11 , further comprising moving the heat transfer fluid returned to the liquid state along the length of each heat pipe of the plurality of heat pipes from the first heat exchanger and the second heat exchanger back into the reactor core.

13. The method of claim 10 , wherein passing the fluid through the open volume defined by the open flow path in the first heat exchanger and the second heat exchanger comprises flowing the fluid along a spiral flow path in the heat exchanger defined by baffles in the first heat exchanger and the second heat exchanger.

14. A nuclear reactor, comprising: a reactor core comprising:
fuel rods; and
heat pipes each comprising closed ends and containing a heat transfer fluid,
each heat pipe of the heat pipes being positioned adjacent to at least one fuel rod of the fuel rods; and

a heat exchanger coupled to the reactor core and comprising a housing having at least one inlet and at least one outlet,
heat pipes extending from the reactor core into the heat exchanger,
the housing defining an undivided open volume through which a single flow path extends between the at least one inlet and at least one outlet,
the undivided open volume of the housing encompassing substantially an entire length of substantially all of the heat pipes within the heat exchanger,
wherein
one of the at least one inlet and the at least one outlet is positioned at a proximal location where the heat exchanger is coupled to the reactor core and
the other of the at least one inlet and the at least one outlet is positioned at a distal location spaced from where the heat exchanger is coupled to the reactor core,

the heat exchanger comprising baffles extending from an exterior portion of the housing of the heat exchanger into the undivided open volume in the flow path between the at least one inlet and the at least one outlet and contacting the heat pipes,
wherein the single flow path is configured such that substantially all of a fluid flowing through the single flow path directly contacts substantially all of the heat pipes of the plurality of heat pipes.

15. The nuclear reactor of claim 14 , wherein each heat pipe of the heat pipes extends along an entire length of the fuel rods.

16. The nuclear reactor of claim 14 , wherein each heat pipe of the heat pipes extends past the fuel rods and into the heat exchanger.

17. The nuclear reactor of claim 14 , further comprising another heat exchanger positioned at and coupled to a first end of the reactor core, the heat exchanger coupled to a second end of the reactor core opposing the first end.

18. The nuclear reactor of claim 14 , wherein the baffles each have at least one heat pipe of the heat pipes extending therethrough.

Assignees

• Battelle Energy Alliance Llc

Inventors

• Mckellar Michael G

Classifications

• G21C5/02 Primary

  Details · CPC title

• G21C11/06

  Reflecting shields, i.e. for minimising loss of neutrons · CPC title

• G21C7/04

  of burnable poisons (burnable poisons in fuel rods G21C3/326) · CPC title

• G21D1/006

  primary side of steam generators (secondary side of steam generators F22B1/00, F22B35/00 or F22B37/00) · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title