Molten fuel reactor thermal management configurations

Patent metadata

Field	Value
Publication number	US-12562287-B2
Application number	US-202217743169-A
Country	US
Kind code	B2
Filing date	May 12, 2022
Priority date	May 2, 2016
Publication date	Feb 24, 2026
Grant date	Feb 24, 2026

Abstract

Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.

First claim

What is claimed is:

1 . A molten salt nuclear reactor comprising:
a substantially frustum-shaped reactor core containing a fissionable fuel salt and having a reactor core bottom and a reactor core top, the reactor core bottom being larger than the reactor core top, the reactor core having a heated fuel salt outlet, a cooled fuel salt inlet, and a thermal center above the cooled fuel salt inlet; at least one heat exchanger that receives heated fuel salt at a heat exchanger fuel salt inlet below the reactor core's heated fuel salt outlet, transfers heat from the fuel salt to a coolant, and discharges the cooled fuel salt at a heat exchanger fuel salt outlet fluidly connected to the reactor core's cooled fuel salt inlet; and wherein the thermal center of the reactor core is at a level below the heat exchanger fuel salt outlet; and wherein the location of the thermal center causes natural circulation in the case of a loss of forced flow while the reactor is in a state of criticality.

2 . The molten salt nuclear reactor of claim 1 wherein the shape of the reactor core is selected from a frustum of a cone, a frustum of a pyramid, a trapezoidal prism or a hyperboloid.

3 . The molten salt nuclear reactor of claim 1 , further comprising:
a containment vessel containing the reactor core and the at least one heat exchanger.

4 . The molten salt nuclear reactor of claim 1 , wherein the location of the thermal center causes natural circulation in the case of a loss of forced flow while the reactor is in a state of subcriticality.

5 . The molten salt nuclear reactor of claim 1 , further comprising:
an upper neutron reflector defining the top of the reactor core; a lower neutron reflector defining the bottom of the reactor core; and at least one inner neutron reflector defining sides of the reactor core, the at least one inner neutron reflector being between the at least one heat exchanger and the reactor core.

6 . The molten salt nuclear reactor of claim 5 , wherein the reactor core's heated fuel salt outlet is a duct between the upper neutron reflector and at least one inner neutron reflector.

7 . The molten salt nuclear reactor of claim 5 , wherein the reactor core's cooled fuel salt inlet is a duct between the lower neutron reflector and at least one inner neutron reflector.

8 . The molten salt nuclear reactor of claim 1 , wherein the at least one heat exchanger is a shell and tube heat exchanger in which the fuel salt flows through the tubes of the shell and tube heat exchanger.

9 . The molten salt nuclear reactor of claim 1 , wherein incoming cold coolant cools a first portion of a containment vessel containing the reactor core and the at least one heat exchanger before the coolant flows into the at least one heat exchanger.

Assignees

• Terrapower Llc

Inventors

• Cisneros Jr Anselmo T
• Johns Christopher J
• Kelleher Brian C
• Kramer Kevin
• Latkowski Jeffery F
• Mcwhirter Jon D

Classifications

• G21C15/28

  Selection of specific coolants (if serving as the moderator G21C5/12; compositions per se C09K5/00; {organic coolants G21C5/123}); {Additions to the reactor coolants, e.g. against moderator corrosion (purification and regeneration of the reactor coolants G21C19/30)} · CPC title

• G21C15/02

  Arrangements or disposition of passages in which heat is transferred to the coolant; {Coolant flow control devices (G21C19/04 takes precedence; coolant flow control through fuel assemblies, e.g. flow restrictors G21C3/322)} · CPC title

• G21C3/54

  Fused salt, oxide or hydroxide compositions · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C1/03

  cooled by a coolant not essentially pressurised, e.g. pool-type reactors · CPC title