Reactor design with controlled thermal neutron flux for enhanced neutron activation potential

Patent metadata

Field	Value
Publication number	US-12288625-B2
Application number	US-202318386378-A
Country	US
Kind code	B2
Filing date	Nov 2, 2023
Priority date	Feb 14, 2020
Publication date	Apr 29, 2025
Grant date	Apr 29, 2025

Abstract

Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons ≤0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.

First claim

What is claimed is:

1. A method to assemble a thermal neutron reactor core, the method comprising:
assembling a plurality of fuel rods, each fuel rod extending parallel to a longitudinally extending central axis of the thermal neutron reactor core and including a composite fuel composition enclosed within a primary containment barrier, wherein the primary containment barrier comprises a seamless cladding tube, a first end cap at a first longitudinal end of the fuel rods, and a second end cap at a second longitudinal end of the fuel rods;
distributing a plurality of intermediate support plates along a longitudinal length of the plurality of fuel rods between the first longitudinal end and the second longitudinal end and attaching each of the plurality of fuel rods to each intermediate support plate, wherein the intermediate support plate includes a plurality of openings extending across a thickness of the respective intermediate support plate from a first side to a second side of the respective intermediate support plate, and wherein, in a plane perpendicular to the longitudinally extending central axis of the thermal neutron reactor core, the plurality of fuel rods are located at nodes of a hexagonal pitch arrangement;
attaching each of the plurality of fuel rods to a first end plate located at the first longitudinal end of the thermal neutron reactor core, the first end plate including a plurality of openings extending across a thickness of the respective intermediate support plate from a first side to a second side of the first end plate, wherein each of the plurality of fuel rods is attached to the first end plate by a first interfacing structure; and
attaching each of the plurality of fuel rods to a second end plate located at the second longitudinal end of the thermal neutron reactor core, the second end plate including a plurality of openings extending across a thickness of the respective intermediate support plate from a first side to a second side of the second end plate, wherein each of the plurality of fuel rods is attached to the second end plate by a second interfacing structure,
wherein the nodes are in a spaced-apart arrangement with the openings between the nodes, the openings forming part of a flow path through the thermal neutron reactor core extending from the first end plate to the second end plate, and
wherein at least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment.

2. The method according to claim 1 , wherein auxiliary equipment includes a control rod or a target delivery system for isotopes.

3. The method according to claim 1 , wherein attaching each of the plurality of fuel rods to each intermediate support plate incudes welding or diffusion bonding.

4. The method according to claim 1 , wherein the first interfacing structure includes a threaded nut threaded onto a threaded connection of the first end cap.

5. The method according to claim 1 , wherein the second interfacing structure includes a threaded nut threaded onto a threaded connection of the second end cap.

6. The method according to claim 1 , wherein the first interfacing structure includes a threaded connection of the first end cap directly threaded into a threaded hole in the first end plate.

7. The method according to claim 1 , wherein the second interfacing structure includes a threaded connection of the second end cap directly threaded into a threaded hole in the second end plate.

8. The method according to claim 1 , wherein the composite fuel composition includes 89-91% BeO, 8.5-10.5% UO 2 , and 0.25-1.0% CeO 2 , and wherein the uranium in the UO 2 includes 80-95% enriched U-235 and the balance is U-234 and U-238.

9. The method according to claim 1 , wherein the composite fuel composition includes 90% BeO, 9.5% UO 2 , and 0.5% CeO 2 , and wherein the uranium in the UO 2 includes 90% enriched U-235 and the balance is U-234 and U-238.

10. The method according to claim 1 , wherein the composite fuel composition has a shape of a cylindrical fuel pellet and a plurality of cylindrical fuel pellets are axially stacked within the seamless cladding tube.

11. The method according to claim 10 , wherein the composite fuel composition in the cylindrical fuel pellet is volumetrically homogeneous.

12. The method according to claim 1 , wherein the first end cap and the second end cap are welded to the seamless cladding tube.

13. The method according to claim 1 , wherein a composition of the first end plate, a composition of the second end plate, and a composition of the plurality of intermediate support plates are each an aluminum alloy or a zirconium alloy.

14. The method according to claim 13 , wherein a composition of the first end plate, a composition of the second end plate, and a composition of the plurality of intermediate support plates are each an aluminum alloy.

15. The method according to claim 1 , wherein a composition of the seamless cladding tube is an aluminum alloy or a zirconium alloy.

16. The method according to claim 13 , wherein a composition of the seamless cladding tube is an aluminum alloy.

17. A method to assemble a thermal neutron fission reactor, the method comprising:
assembling the thermal neutron reactor core according to claim 1 ;
conformally mating a radially outer surface of the thermal neutron reactor core to a radially inner surface of a reflector; and
connecting the first end plate to a first brace attached to an inner surface of a pressure vessel and connecting the second end plate to a second brace attached to the inner surface of the pressure vessel.

Assignees

• Bwxt Advanced Tech Llc

Inventors

• Gramlich Craig D
• Russell Ii William E

Classifications

• G21C3/334

  Assembling {, maintenance or repair of} the bundles {(assembling, maintenance or repair of other reactor components G21C19/207)} · CPC title

• G21G1/02

  in nuclear reactors (by thermonuclear reactions G21B; conversion of nuclear fuel G21C) · CPC title

• G21C3/16

  Details of the construction within the casing · CPC title

• G21C23/00

  Adaptations of reactors to facilitate experimentation or irradiation · CPC title

• G21C5/10

  Means for supporting the complete structure {(arrangements for supporting vessels and core-structures G21C13/024)} · CPC title