Apparatus and method for generating medical isotopes

Patent metadata

Field	Value
Publication number	US-10332646-B2
Application number	US-201113373899-A
Country	US
Kind code	B2
Filing date	Dec 5, 2011
Priority date	Dec 5, 2011
Publication date	Jun 25, 2019
Grant date	Jun 25, 2019

Abstract

An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

First claim

What we claim is:

1. A nuclear reaction system comprising:
an annular solution vessel having an inner wall defining an inner circumference and an opposed outer wall defining an outer circumference, the inner wall and outer wall defining a first volume therebetween and a second volume within the inner wall, both walls extending along a shared central axis;
an aqueous fissile solution within the first volume;
a first annular cooling jacket containing cooling fluid in thermal communication with the aqueous fissile solution through an inner intermediate wall, the first annular cooling jacket defined by the inner wall of the annular solution vessel and the inner intermediate wall;
a second annular cooling jacket containing cooling fluid in thermal communication with the aqueous fissile solution through an outer intermediate wall, the second annular cooling jacket defined by the outer wall of the annular solution vessel and the outer intermediate wall;
a particle emitter positioned within the second volume and configured to emit neutrons passing radially outward from the volume through the first annular cooling jacket to the aqueous fissile solution; and
a neutron multiplier disposed within the first annular cooling jacket between the inner wall of the annular solution vessel and the inner intermediate wall and configured to absorb the neutrons from the particle emitter and provide more neutrons than it absorbs to the aqueous fissile solution, wherein the neutron multiplier material is selected from the group consisting of beryllium and depleted uranium and natural uranium.

2. The nuclear reaction system of claim 1 wherein the annular solution vessel contains low enriched uranium.

3. The nuclear reaction system of claim 2 wherein the annular solution vessel contains a mixture of water and at least one of uranyl nitrate, uranyl sulfate, uranyl fluoride or uranyl phosphate.

4. The nuclear reaction system of claim 1 further including a particle source positioned to direct charged particles into the particle emitter proximate to the annular solution vessel for generation of neutrons from the particle emitter to be received in the annular solution vessel.

5. The nuclear reaction system of claim 1 wherein the neutron multiplier material provides for a neutron multiplication of substantially 1.5-3.0.

6. The nuclear reaction system of claim 5 further including a neutron moderator material positioned between the inner wall of the annular solution vessel and the inner intermediate wall in coaxial separation from the neutron multiplier.

7. The nuclear reaction system of claim 1 further including a reflecting material concentrically outside of the annular solution vessel.

8. The nuclear reaction system of claim 1 wherein the cooling fluid delivered to the first and second annular jackets is chilled water.

9. The nuclear reaction system of claim 1 wherein the particle emitter is a target material receiving a charged particle from a particle source.

10. The nuclear reaction system of claim 1 further comprising a feedback control system comprising temperature probes in thermal communication with at least one of the water jackets and a valve in fluid communication with the aqueous fissile solution, the feedback control system configured to actuate the valve and adjust a level of the aqueous fissile solution within the first volume based on a temperature sensed by the temperature probes.

11. A nuclear reaction system comprising:
an annular solution vessel having an inner wall defining an inner circumference and an opposed outer wall defining an outer circumference, the inner wall and outer wall defining a first volume therebetween and a second volume within the inner wall, both walls extending along a shared central axis;
an aqueous fissile solution within the first volume;
a first annular cooling jacket containing cooling fluid in thermal communication with the aqueous fissile solution through an inner intermediate wall, the first annular cooling jacket defined by the inner wall of the annular solution vessel and the inner intermediate wall;
a second annular cooling jacket containing cooling fluid in thermal communication with the aqueous fissile solution through an outer intermediate wall, the second annular cooling jacket defined by the outer wall of the annular vessel and the outer intermediate wall;
a particle emitter positioned within second volume and configured to emit neutrons passing radially outward from the volume through the first annular cooling jacket to the aqueous fissile solution; and
a feedback control system comprising temperature probes in thermal communication with at least one of the water jackets and a valve in fluid communication with the aqueous fissile solution, the feedback control system configured to actuate the valve and adjust a level of the aqueous fissile solution within the first volume based on a temperature sensed by the temperature probes.

12. The nuclear reaction system of claim 11 wherein the annular solution vessel contains low enriched uranium.

13. The nuclear reaction system of claim 12 wherein the annular solution vessel contains a mixture of water and at least one of uranyl nitrate, uranyl sulfate, uranyl fluoride or uranyl phosphate.

14. The nuclear reaction system of claim 11 further including a particle source positioned to direct charged particles into the particle emitter proximate to the annular solution vessel for generation of neutrons from the particle emitter to be received in the annular solution vessel.

15. The nuclear reaction system of claim 11 further comprising a neutron multiplier disposed within the first annular cooling jacket between the inner wall of the annular solution vessel and the inner intermediate wall and configured to absorb the neutrons from the particle emitter and provide more neutrons than it absorbs to the aqueous fissile solution, wherein the neutron multiplier material is selected from the group consisting of beryllium and depleted uranium and natural uranium.

16. The nuclear reaction system of claim 15 wherein the neutron multiplier material provides for a neutron multiplication of substantially 1.5-3.0.

17. The nuclear reaction system of claim 16 further including a neutron moderator material positioned between the inner wall of the annular solution vessel and the inner intermediate wall in coaxial separation from the neutron multiplier.

18. The nuclear reaction system of claim 11 further including a reflecting material concentrically outside of the annular solution vessel.

19. The nuclear reaction system of claim 11 wherein the cooling fluid delivered to the first and second annular jackets is chilled water.

20. The nuclear reaction system of claim 11 wherein the particle emitter is a target material receiving a charged particle from a particle source.

Assignees

• Piefer Gregory Richard
• Heltemes Thad Alexander
• Van Abel Eric Nicholas
• Radel Ross Francis
• Wisconsin Alumni Res Found

Inventors

• Piefer Gregory Richard
• Heltemes Thad Alexander
• Van Abel Eric Nicholas
• Radel Ross Francis

Classifications

• H05H2277/116

  Isotope production · CPC title

• H05H3/06

  Generating neutron beams (targets for producing nuclear reactions H05H6/00; neutron sources G21G4/02) · CPC title

• G21G1/10

  by bombardment with electrically charged particles (irradiation devices G21K5/00) · CPC title

• G21G2001/0063

  Iodine · CPC title

• G21G2001/0042

  Technetium · CPC title