Granted Patent B2

US 12,525,366 · App. 18/756,611 · Granted Jan 13, 2026

Inventors: Bret Kugelmass (Washington, DC); Mark Blomstrom (Northbridge, MA); Charles Cole (Washington, DC); Phoebe Lind (Washington, DC); Daniel Theobald (Washington, DC)

Assignee: Last Energy Inc.

G21C9/022G21C11/088G21C15/18G21C15/28G21C1/02G21C3/54

Abstract

Claims (130)

1 . A system comprising:

a shield:

defining an internal volume; and

configured to absorb radiation;

a nuclear reactor comprising:

a pressure vessel:

arranged within the internal volume; and

defining:

an upper region;

a lower region arranged below the upper region; and

an upper seal slot interposed between the upper region and the lower region;

a lower seal slot aligned with and vertically offset from the upper seal slot along a vertical axis of the pressure vessel;

a nuclear fuel arranged within the lower region of the pressure vessel and configured to heat a working fluid entering the pressure vessel, via a fission reaction; and

a set of control rods configured to transition between the upper region and the lower region of the pressure vessel to moderate the fission reaction within the nuclear fuel;

a metallic fluid:

comprising a mixture of metals comprising:

a first proportion of lead configured to decrease an effective melting temperature of the metallic fluid and absorb gamma radiation emitted by the nuclear fuel;

a second proportion of bismuth configured to absorb gamma radiation emitted by the nuclear fuel and to increase an effective boiling temperature of the metallic fluid; and

a third proportion of cadmium configured to absorb neutron radiation emitted by the nuclear fuel;

in a liquid state within an operating temperature range of the nuclear reactor; and

configured to:

occupy an interstitial volume between the shield and the pressure vessel;

transfer thermal energy from the pressure vessel into the shield to distribute heat around the pressure vessel within the operating temperature range; and

absorb radiation emitted by the nuclear reactor; and

a first melt seal:

arranged in the upper seal slot of the pressure vessel;

configured to retain a volume of the metallic fluid within the interstitial volume between the shield and the pressure vessel during operation of the nuclear reactor; and

configured to unseal from the upper seal slot to release metallic fluid, in the volume of the metallic fluid, into the lower region of the pressure vessel, the volume of the metallic fluid displacing the working fluid away from the nuclear fuel, in response to temperatures within the pressure vessel exceeding the operating temperature range; and

a second melt seal:

arranged in the lower seal slot of the pressure vessel;

configured to cooperate with the first melt seal to retain the volume of the metallic fluid within the interstitial volume between the shield and the pressure vessel during operation of the nuclear reactor; and

configured to unseal from the lower seal slot to release metallic fluid, in the volume of the metallic fluid, into the lower region of the pressure vessel in response to temperatures within the pressure vessel exceeding the operating temperature range.

2 . The system of claim 1 :

wherein the pressure vessel defines the lower seal slot:

proximal a base of the pressure vessel.

3 . The system of claim 1 :

wherein the nuclear reactor is configured to operate within the operating temperature range between 150 degrees Celsius and 450 degrees Celsius; and

wherein the metallic fluid coolant is characterized by an effective boiling temperature greater than the operating temperature range to maintain homogeneity of the mixture of metals at temperatures outside of the operating temperature range.

4 . The system of claim 1 , wherein the pressure vessel comprises:

a fluid inlet configured to:

receive the working fluid from an external water reservoir, via a working fluid supply line, at a first flow rate; and

direct the working fluid toward the nuclear fuel to moderate the fission reaction and absorb thermal energy from the nuclear fuel; and

a fluid outlet configured to:

emit the working fluid from the pressure vessel to an external thermal power generation system for conversion of thermal energy into electricity, at a second flow rate proportional to the first flow rate; and

cooperate with the fluid inlet to maintain pressures within the pressure vessel within a target pressure range.

5 . The system of claim 1 :

wherein the pressure vessel defines a second upper seal slot interposed between the upper region and the lower region of the pressure vessel;

wherein the first melt seal comprises a first melt plug:

arranged in a first lateral position in the upper seal slot of the pressure vessel;

laterally offset from a vertical axis of the pressure vessel; and

configured to release a first subvolume of the metallic fluid into the lower region of the pressure vessel in response to the temperature within the pressure vessel exceeding the operating temperature range; and

wherein the second melt seal comprises a second melt plug:

arranged in a second lateral position in the second upper seal slot of the pressure vessel;

laterally offset from the vertical axis of the pressure vessel opposite the first melt plug; and

configured to unseal from the lower seal slot to release a second subvolume of the metallic fluid into the lower region of the pressure vessel in response to the temperature within the pressure vessel exceeding the operating temperature range.

6 . The system of claim 1 :

wherein the nuclear fuel

a set of fuel rods, each fuel rod in the set of fuel rods:

defining a minimum diameter within a target diameter range;

defining a lateral pitch distance:

greater than the minimum diameter; and

less than a maximum diameter of the lower region of the pressure vessel;

configured to house a fissile material; and

arranged in a radial pattern about a vertical axis of the pressure vessel.

7 . The system of claim 6 :

wherein the set of fuel rods are arranged at a first height within the lower region of the pressure vessel; and

wherein the first melt seal is:

arranged at a second height, greater than the first height, between the upper region and the lower region of the pressure vessel; and

configured to release metallic fluid, in the volume of the metallic fluid, into the lower region of the pressure vessel at a first flow rate, corresponding to the first size and the second height, to reduce impact between the volume of the metallic fluid and the set of fuel rods.

8 . The system of claim 1 , wherein the mixture comprises:

a fourth proportion of tin configured to decrease a viscosity of the metallic fluid.

9 . The system of claim 1 , wherein the metallic fluid:

forms a eutectic alloy;

forms the effective melting temperature of the metallic fluid between 150 degrees Celsius and 250 degrees Celsius; and

forms the effective boiling temperature of the metallic fluid exceeding the operating temperature range of the nuclear reactor.

10 . The system of claim 1 , wherein the metallic fluid comprises:

the first proportion of lead configured to absorb gamma radiation emitted by the nuclear fuel succeeding an over-temperature event;

the second proportion of bismuth configured to absorb gamma radiation emitted by the nuclear fuel succeeding the over-temperature event; and

the third proportion of cadmium configured to absorb neutron radiation emitted by the nuclear fuel succeeding the over-temperature event.

11 . A system comprising:

a nuclear reactor comprising:

a pressure vessel defining:

an upper region;

a lower region arranged below the upper region;

an upper seal slot interposed between the upper region and the lower region; and

a lower seal slot aligned with and vertically offset from the upper seal slot along a vertical axis of the pressure vessel;

a nuclear fuel arranged within the lower region of the pressure vessel and configured to heat a working fluid entering the pressure vessel, via a fission reaction; and

a set of control rods configured to transition between the upper region and the lower region of the pressure vessel to moderate the fission reaction within the nuclear fuel;

a metallic fluid:

comprising:

a first proportion of lead configured to decrease an effective melting temperature of the metallic fluid and absorb gamma radiation emitted by the nuclear fuel;

a second proportion of bismuth configured to absorb gamma radiation emitted by the nuclear fuel and to increase an effective boiling temperature of the metallic fluid; and

a third proportion of cadmium configured to absorb neutron radiation emitted by the nuclear fuel;

in a liquid state within an operating temperature range of the nuclear reactor; and

configured to:

occupy an interstitial volume between a shield and the pressure vessel; and

absorb radiation emitted by the nuclear reactor;

a first melt seal:

arranged in the upper seal slot of the pressure vessel;

configured to retain a volume of the metallic fluid within the interstitial volume between the shield and the pressure vessel during operation of the nuclear reactor; and

configured to unseal from the upper seal slot to release metallic fluid, in the volume of the metallic fluid, into the lower region of the pressure vessel, the volume of the metallic fluid displacing the working fluid away from the nuclear fuel, in response to temperatures within the pressure vessel exceeding the operating temperature range; and

a second melt seal:

arranged in the lower seal slot of the pressure vessel;

configured to cooperate with the first melt seal to retain the volume of the metallic fluid within the interstitial volume between the shield and the pressure vessel during operation of the nuclear reactor; and

configured to unseal from the lower seal slot to release metallic fluid, in the volume of the metallic fluid, into the lower region of the pressure vessel in response to temperatures within the pressure vessel exceeding the operating temperature range.

12 . A system comprising:

a nuclear reactor comprising:

a pressure vessel defining:

an upper region;

a lower region arranged below the upper region;

a first seal slot interposed between the upper region and the lower region; and

a second seal slot aligned with and vertically offset from the first seal slot along a vertical axis of the pressure vessel; and

a nuclear fuel arranged within the lower region of the pressure vessel and configured to heat a working fluid entering the pressure vessel, via a fission reaction; and

a metallic fluid:

comprising:

a first proportion of lead configured to decrease an effective melting temperature of the metallic fluid and absorb gamma radiation emitted by the nuclear fuel;

a second proportion of bismuth configured to absorb gamma radiation emitted by the nuclear fuel and to increase an effective boiling temperature of the metallic fluid; and

a third proportion of cadmium configured to absorb neutron radiation emitted by the nuclear fuel;

in a liquid state within an operating temperature range of the nuclear reactor; and

configured to:

occupy an interstitial volume between a shield and the pressure vessel; and

absorb radiation emitted by the nuclear reactor; and

a first melt seal:

arranged in the first seal slot of the pressure vessel;

configured to retain metallic fluid within the interstitial volume between the shield and the pressure vessel during operation of the nuclear reactor; and

configured to unseal from the first seal slot to release metallic fluid into the lower region of the pressure vessel in response to temperatures within the pressure vessel exceeding the operating temperature range to displace the working fluid away from the nuclear fuel; and

a second melt seal:

arranged in the second seal slot of the pressure vessel;

configured to retain metallic fluid within the interstitial volume between the shield and the pressure vessel during operation of the nuclear reactor; and

configured to unseal from the second seal slot to release metallic fluid into the lower region of the pressure vessel in response to temperatures within the pressure vessel exceeding the operating temperature range to displace the working fluid away from the nuclear fuel.

Assignments (3)

Continuity (2)

References Cited (24)