Nuclear reactors having liquid metal alloy fuels and/or moderators

Patent metadata

Field	Value
Publication number	US-2023377763-A1
Application number	US-202318329490-A
Country	US
Kind code	A1
Filing date	Jun 5, 2023
Priority date	Oct 15, 2019
Publication date	Nov 23, 2023
Grant date	—

Abstract

Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.

First claim

I/We claim:

1 . A fuel rod for a nuclear reactor, comprising:
a wall defining a chamber, wherein the chamber is configured to contain a liquid nuclear fuel; and a filter fluidly coupled to the chamber for receiving gaseous products generated by the liquid nuclear fuel, wherein the filter includes a port positioned to vent one or more first ones of the gaseous products from the chamber, and wherein the filter includes a filter member positioned to capture one or more second ones of the gaseous products.

2 . The fuel rod of claim 1 wherein the wall includes a first wall portion and a second wall portion, wherein the first wall portion includes a greater amount of a neutron-absorbing material than the second wall portion.

3 . The fuel rod of claim 2 wherein the filter is integrally formed with the wall, and wherein the first wall portion is closer to the filter than the second wall portion.

4 . The fuel rod of claim 3 , further comprising the liquid nuclear fuel, wherein the liquid nuclear fuel is configured to circulate within the chamber from proximate the first wall portion to proximate the second wall portion.

5 . The fuel rod of claim 2 , further comprising the liquid nuclear fuel, wherein the liquid nuclear fuel remains subcritical proximate the first wall portion.

6 . The fuel rod of claim 1 wherein the filter member is configured to physically capture the one or more of the second gaseous products.

7 . The fuel rod of claim 1 wherein the filter member is configured to bind to the one or more of the second gaseous products.

8 . The fuel rod of claim 1 wherein the first ones of the gaseous products are reactive fission products, and wherein the second ones of the gaseous products are non-reactive fission products.

9 . The fuel rod of claim 8 wherein the reactive fission products comprise xenon and/or krypton, and wherein the non-reactive fission products comprise one or more noble gases.

10 . The fuel rod of claim 1 wherein the filter member is one of a plurality of filter members, and wherein individual ones of the filter members are positioned to capture different ones of the second ones of the gaseous products.

11 . The fuel rod of claim 10 wherein the second ones of the gaseous products are non-reactive fission products.

12 . The fuel rod of claim 10 wherein the filter defines a serpentine flow path, and wherein the filter members are positioned serially along the flow path.

13 . The fuel rod of claim 1 , further comprising the liquid nuclear fuel, wherein the liquid nuclear fuel is a uranium-iron liquid metal (UI-LM) alloy.

14 . The fuel rod of claim 13 wherein the UI-LM alloy is enriched to 19.5 weight percentage or less uranium-235 (U-235).

15 . A fuel rod for a nuclear reactor, comprising:
a wall defining a chamber, wherein the chamber includes an inactive region and an active region, wherein a first portion of the wall adjacent the inactive region includes a greater amount of a neutron-absorbing material than a second portion of the wall adjacent the inactive region; and a liquid nuclear fuel contained within the chamber, wherein the liquid nuclear fuel is configured to remain subcritical within the inactive region, wherein the liquid nuclear fuel is configured to undergo a fission reaction within the active region, and wherein the liquid nuclear fuel is configured to circulate within the chamber between the active region and the inactive region.

16 . The fuel rod of claim 15 , further comprising a filter fluidly coupled to the chamber for receiving gaseous products generated by the liquid nuclear fuel, wherein the filter includes a port positioned to vent one or more first ones of the gaseous products from the chamber, and wherein the filter includes a filter member positioned to capture one or more second ones of the gaseous products.

17 . The fuel rod of claim 16 wherein the first ones of the gaseous products are reactive fission products that inhibit the fission reaction of the liquid nuclear fuel.

18 . The fuel rod of claim 17 wherein the second ones of the gaseous products are non-reactive fission products, and wherein the liquid nuclear fuel is a uranium-iron liquid metal (UI-LM) alloy.

19 . A fuel rod for a nuclear reactor, comprising:
a wall defining a chamber, wherein the chamber is configured to contain a liquid nuclear fuel, wherein the liquid nuclear fuel is configured to undergo a fission reaction within the chamber that generates heat, reactive fission products, and non-reactive fission products; and a filter fluidly coupled to the chamber for receiving the reactive fission products and the non-reactive fission products generated by the liquid nuclear fuel, wherein the filter includes a port positioned to vent one or more of the reactive fission products from the chamber, and wherein the filter includes a filter member positioned to capture one or more of the non-reactive fission products.

20 . The fuel rod of claim 19 wherein the reactive fission products include xenon and/or krypton, wherein the non-reactive fission products include noble gases, and wherein the filter defines a serpentine flow path, and wherein the filter member is positioned along the flow path.

Assignees

• Nuscale Power Llc

Inventors

• Botha Frederick
• Keppen Jackson
• Galimov Azat Yumadilovich
• Mirsky Steven M

Classifications

• G21C1/22 Primary

  using liquid or gaseous fuel · CPC title

• G21C11/088

  consisting of a stagnant or a circulating fluid · CPC title

• G21C15/257

  using heat-pipes {(in general F28D, F28F)} · CPC title

• G21C7/26 Primary

  by displacement of the moderator or parts thereof {by changing the moderator concentration} · CPC title

• G21C3/041 Primary

  Means for removal of gases from fuel elements · CPC title