IP Library Granted Patent US 11,817,225
Granted Patent B2
US 11,817,225 · App. 17/852,434 · Granted Nov 14, 2023

Functionally graded lattice cermet fuel structure with shape corresponding to a mathematically-based periodic solid, particularly for nuclear thermal propulsion

Inventors: Benjamin D. Fisher (Lynchburg, VA); John R. Salasin (Lynchburg, VA); Craig D. Gramlich (Forest, VA); Jonathan K. Witter (Forest, VA)
Assignee: BWXT Advanced Technologies LLC
G21C3/044G21C3/04G21C3/42G21C3/28G21C3/30G21C21/02G21D5/02
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Quick Facts
Patent No.
US 11,817,225
App. No.
17/852,434
Granted
Nov 14, 2023
Kind
B2
Abstract

Nuclear propulsion fission reactor structure has an active core region including fuel element structures, a reflector with rotatable neutron absorber structures (such as drum absorbers), and a core former conformal mating the outer surface of the fuel element structures to the reflector. Fuel element structures are arranged abutting nearest neighbor fuel element structures in a tri-pitch design. Cladding bodies defining coolant channels are inserted into and joined to lower and upper core plates to from a continuous structure that is a first portion of the containment structure. The body of the fuel element has a structure with a shape corresponding to a mathematically-based periodic solid, such as a triply periodic minimal surface (TPMS) in a gyroid structure. The nuclear propulsion fission reactor structure can be incorporated into a nuclear thermal propulsion engine for propulsion applications, such as space propulsion.

Claims (35)

1. A nuclear fuel lattice structure, comprising:

a body having a structure including a plurality of webbings having outer surfaces that define a network of interconnected channels located within an envelope surface of the body,

wherein a baseline of the webbings is an implicit surface of a mathematically-based periodic solid,

wherein the mathematically-based periodic solid is a triply periodic minimal surface (TPMS),

wherein at least a portion of the channels extend from a first outer surface of the body to a second outer surface of the body,

wherein the structure has a volumetric density of 35% to 85%,

wherein a composition of the structure includes a nuclear fissionable fuel having an enrichment of up to 20%, and

wherein a specific enrichment of the structure (% enrichment per unit volume) is constant ±2%.

2. The nuclear fuel lattice structure according to claim 1 , wherein the triply periodic minimal surface (TPMS) is a gyroid structure, and wherein the implicit surface is defined by a gyroid equation (sin x cos y+sin y cos z+sin z cos x)=0.

3. The nuclear fuel lattice structure according to claim 2 , wherein each webbing has a thickness relative to the baseline, and, within the body, the thickness of the webbing varies in accordance with a vector field.

4. The nuclear fuel lattice structure according to claim 3 , wherein the thickness of the webbings is symmetric relative to the baseline.

5. The nuclear fuel lattice structure according to claim 1 , wherein a uranium content of the nuclear fissionable fuel varies by spatial location in the body.

6. The nuclear fuel lattice structure according to claim 5 , wherein the variation in uranium content by spatial location in the body includes increasing a content of U235 due to an increased density of the lattice.

7. The nuclear fuel lattice structure according to claim 1 , wherein the mathematically-based periodic solid is biased to effect a flow rate of a medium flowing through the network of interconnected channels.

8. The nuclear fuel lattice structure according to claim 1 , wherein the body is disc-shaped and occupies a volume that includes a radial side surface corresponding to a thickness of the body between the first outer surface and the second outer surface.

9. The nuclear fuel lattice structure according to claim 1 , wherein the triply periodic minimal surface (TPMS) is a Schwarz minimal surface.

10. The nuclear fuel lattice structure according to claim 1 , wherein the nuclear fissionable fuel is high-assay low-enriched uranium (HALEU) with a U 235 assay equal to or greater than 5 percent to equal to or lower than 20 percent.

11. The nuclear fuel lattice structure according to claim 1 , wherein the nuclear fissionable fuel includes uranium oxide that is less than 20% enriched, uranium with 10 wt. % molybdenum (U-10Mo), uranium nitride (UN), or a cermet thereof.

12. The nuclear fuel lattice structure according to claim 3 , wherein the thickness of the webbings is asymmetric relative to the baseline.

13. A nuclear fuel segment, comprising:

the nuclear fuel lattice structure according to claim 1 ; and

a cladding layer deposited on the outer surfaces of the plurality of webbings that define the network of interconnected channels.

14. The nuclear fuel segment according to claim 13 , wherein the cladding layer has a composition including molybdenum, tungsten, rhenium, tantalum, hafnium and alloys thereof, including carbides.

15. A nuclear reactor structure, comprising:

an active core region including a plurality of nuclear fuel segments according to claim 13 ,

wherein the plurality of nuclear fuel segments are arranged along an axial centerline defining a longitudinal axis of the nuclear reactor structure.

16. The nuclear reactor structure according to claim 15 , wherein the network of interconnected channels in the body of adjacent nuclear fuel segments are aligned to provide fluid communication from a first end surface of the active core to a second end surface of the active core.

17. A nuclear thermal propulsion engine, comprising:

the nuclear reactor structure according to claim 15 , wherein the nuclear reactor structure is housed within an interior volume of a hull;

shielding;

a reservoir for cryogenically storing propulsion gas;

turbomachinery; and

a nozzle,

wherein the shielding, the turbomachinery, and the reservoir are operatively mounted to a first end of the hull to provide a flow path from the reservoir to the nuclear reactor structure, and

wherein the nozzle is operatively mounted to a second end of the hull to provide a flow path for superheated propulsion gas exiting the nuclear thermal propulsion engine.

Assignments (1)
SECURITY INTEREST Recorded Nov 10, 2025
From: BWXT ADVANCED TECHNOLOGIES LLC; BWXT ISOTOPE TECHNOLOGY GROUP, INC.; BWXT NUCLEAR ENERGY, INC.
To: WELLS FARGO BANK, NATIONAL ASSOCIATION, AS ADMINISTRATIVE AGENT
Reel/Frame 073531/0358 →
Continuity (3)
Division 16835388 · Mar 31, 2020
Provisional Application 62827706 · Apr 1, 2019
Related Publication 20220351870A1 · Nov 3, 2022