IP Library Granted Patent US 11,848,116
Granted Patent B2
US 11,848,116 · App. 17/750,655 · Granted Dec 19, 2023

Irradiating target material located in a surrogate fuel bundle in a CANDU reactor for isotope production

Inventors: Thomas G. Onderwater (Peterborough, CA); Benjamin D. Fisher (Lynchburg, VA)
Assignee: BWXT Isotope Technology Group, Inc.
G21G1/02G21C3/326G21C23/00G21C1/16G21G1/001G21G2001/0036G21G2001/0042
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Quick Facts
Patent No.
US 11,848,116
App. No.
17/750,655
Granted
Dec 19, 2023
Kind
B2
Abstract

A fuel bundle surrogate for the irradiation of a target material, having a plurality of tube sheaths, each tube sheath being parallel to a longitudinal center axis of the fuel bundle surrogate, a plurality of end caps, a pair of end plates, wherein the end plates are disposed at opposing ends of the plurality of tube sheaths, and a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, wherein the first target is disposed in a first tube sheath, and wherein the first tube sheath of the plurality of tube sheaths comprises an elongated thickened wall portion and a pair of annular end portions, each annular end portion being disposed on a corresponding end of the thickened wall portion and having a wall thickness that is less than a wall thickness of the thickened wall portion.

Claims (28)

1. A method of irradiating a target material in a heavy water reactor for the production of an isotope, comprising the steps of:

providing a first target comprised of a first target material suitable for producing the isotope by way of a neutron capture event, the first target being disposed within a surrogate fuel bundle;

placing the surrogate fuel bundle in a pressure tube of a fuel channel of the heavy water reactor along with a plurality of non-fissile bundles axially aligned with the surrogate fuel bundle so as to position the surrogate fuel bundle at a selected location in the pressure tube; and

irradiating the target.

2. The method of claim 1 , wherein the heavy water reactor is a CANDU reactor.

3. The method of claim 1 , further comprising the step of removing the surrogate fuel bundle after a predetermined residency time in a flux field of the reactor, whereby the first target is irradiated.

4. The method of claim 3 , further comprising transferring the irradiated first target to a processing facility.

5. The method of claim 1 , wherein the step of providing a target further comprises:

providing the surrogate fuel bundle in a form including a plurality of tube sheaths that extends between a pair of opposed end plates; and

placing the target into a first one of the tube sheaths.

6. The method of claim 5 , further comprising providing a non-fissile material in the surrogate fuel bundle.

7. The method of claim 5 , further comprising the steps of:

providing a second target comprised of a second material suitable for producing a radioisotope by way of a neutron capture event; and

placing the second target into a second sheath tube of the plurality of sheath tubes of the surrogate fuel bundle.

8. The method of claim 1 , wherein the step of providing a first target further comprises providing an outer capsule defining an interior volume, wherein the first target material is disposed in the interior volume.

9. The method of claim 8 , wherein the outer capsule is comprised of the first target material.

10. The method of claim 1 , wherein the placing step involves placing the surrogate fuel bundle in a primary fluid side of the pressure tube.

11. The method of claim 1 , wherein the placing step involves placing the surrogate fuel bundle in a secondary fluid side of the pressure tube.

12. The method of claim 6 , wherein the non-fissile material is placed in a radially outer sheath of the surrogate fuel bundle relative to the target.

13. The method of claim 1 , wherein at least one fissile bundle is located in said pressure tube in axial alignment with said surrogate fuel bundle.

14. The method of claim 1 , wherein at least one of the plurality of non-fissile bundles is located upstream of the surrogate fuel bundle and at least another one of the plurality of non-fissile bundles is located downstream of the surrogate fuel bundle in the pressure tube.

15. The method of claim 1 , wherein the surrogate fuel bundle contains a plurality of targets of the first target material.

16. The method of claim 15 , wherein the first target material comprises Mo-98.

17. The method of claim 1 , further comprising the step of:

removing the fuel bundle surrogate from the pressure tube after the target is irradiated.

18. The method of claim 17 , wherein the removing step further comprises:

leaving a second fuel bundle surrogate in the pressure tube after the fuel bundle surrogate is removed so that a second target comprised of a second target material suitable for producing the isotope by way of a neutron capture event may be further irradiated.

19. The method of claim 18 , wherein the first target material and the second target material each comprise Mo-98.

Assignments (2)
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 →
ASSIGNMENT OF ASSIGNOR'S INTEREST Recorded Jul 26, 2022
From: FISHER, BENJAMIN D.; ONDERWATER, THOMAS G.
To: BWXT ISOTOPE TECHNOLOGY GROUP, INC.
Reel/Frame 060623/0532 →
Continuity (3)
Division 16052964 · Aug 2, 2018
Provisional Application 62540444 · Aug 2, 2017
Related Publication 20220293291A1 · Sep 15, 2022