Neutron-capture therapy apparatus and method

• US 5,433,693 A
• Filed: 12/31/1992
• Issued: 07/18/1995
• Est. Priority Date: 12/31/1992
• Status: Expired due to Fees

• Current Assignee: Karl O. Ott
• Original Assignee: Karl O. Ott
• Inventors: Ott, Karl O.
• Primary Examiner(s): Kamm, William E.
• Assistant Examiner(s): Lacyk, John P.
• Application Number:
  US07/998,994
• Time in Patent Office: 929 Days
• Field of Search: 600/1-8
• US Class Current: 600/1
• CPC Class Codes: A61N 2005/109 Neutrons
• CPC Class Codes: A61N 2005/1095 Elements inserted into the radiation path within the system, e.g. filters or wedges
• CPC Class Codes: A61N 5/10 X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy A61N5/01 takes precedence
• CPC Class Codes: A61N 5/1079 Sharing a beam by multiple treatment stations

Abstract

Patient treatment rooms are circularly spaced around a nuclear reactor core. Suitable shielding is provided between the rooms and the core, with neutron transmission passageways provided in the shielding from the core to provide space for appropriate collimating equipment. The core is generally cylindrical and multi-regional, with the inner two or three regions containing nuclear fuel, the inner core producing most of the fission neutrons, the first core ring containing a low enrichment fuel, and the third containing thorium or depleted uranium metal or some other heavy metal for inelastic scattering of neutrons and gamma ray absorption. Two moderator rings, each containing a different moderator liquid composition with variable thermal neutron absorbers and gamma ray absorbers, surrounding the multi-regional core. A heavy metal gamma ray shield surrounds the second moderator ring. The arrangement constricts the neutron spectrum in the reactor itself to transmit only epithermal neutrons to the patients, without the typical spectrum shaping filters normally contemplated for use between reactors and treatment subjects.

Claims

1. Therapy apparatus comprising:

a fast nuclear fission reactor with a reactor core as a source of fast and epithermal neutrons;

material around the reactor core for inelastic and elastic down-scattering of fast neutrons, such material having a macroscopic inelastic neutron scattering cross section at least as large as that of metallic bismuth;

adjustable moderators with 1/v-absorber combination to optimize epithermal neutron spectra for different tumors;

shielding media surrounding the reactor;

a plurality of neutron transmission passageways through said media; and

treatment stations outside the media at the ends of the passageways.

2. The apparatus of claim 1 and further comprising:

collimating devices in the passageways to direct epithermal neutrons from the reactor to predetermined spots at the treatment stations.

3. The apparatus of claim 1 wherein:

the treatment stations are circularly spaced about the reactor in a horizontal plane.

4. The apparatus of claim 1 and wherein:

the moderator-absorber combinations are liquid media within distinct sectors, and

the liquid media are between the source and the treatment station in at least some of the sectors, the moderator-absorber combination in one sector being separate from the moderator-absorber combination in another sector.

5. The apparatus of claim 1 wherein:

the treatment stations are circularly spaced about the source in two vertically spaced horizontal planes, and

radiation shielding media is in the space between the planes.

6. The apparatus of claim 5 and wherein:

human target supports are located at the stations at the lower one of the planes and include lifts to lift a patent in the treatment station to a point adjacent the end of the passageway at the treatment station.

7. The apparatus of claim 1 and wherein the nuclear reactor comprises:

a first central core region including enriched uranium;

a second core region in the form of a cylindrical ring around said central core region and comprising a nuclear fuel of a lower enrichment than the central core region;

a third region in the form of a cylindrical ring around the second core region and containing a heavy metal for inelastic and elastic scattering of neutrons and for gamma ray absorption;

a first moderator region around the third region and containing a liquid moderator; and

a second moderator region around the first moderator region and containing a liquid moderator.

8. The apparatus of claim 7 and wherein:

the first core region contains uranium enriched to 20% or less;

the second core region contains a low enrichment uranium fuel, about 4% U-235, and about 96% U-238; and

the heavy metal in the third region contains depleted uranium metal about 0.23% U-235 in about 99.77% U-238, or thorium metal.

9. The apparatus of claim 7 and wherein:

the first core region contains uranium enriched to 20% or less;

the second core region contains a low enrichment uranium fuel, about 4% U-235, and about 96% U-238; and

the heavy metal in the third region is non-fissionable.

10. The apparatus of claim 7 and wherein:

the first core region has a radius of about 30 cm;

the second core region has an outer radius of about 45 cm; and

the third region has an outer radius of about 60 cm.

11. The apparatus of claim 7 and wherein:

the liquid in the first moderator region is water (H₂ O) laced with Li or boron; and

the liquid in the second moderator region is D₂ O laced with Li or boron.

12. The apparatus of claim 11 and wherein:

the first moderator region is ring shaped and about 10 to 20 cm thick; and

the second moderator region is ring shaped and about 30 to 40 cm thick.

13. The apparatus of claim 7 and further comprising:

a cylindrical gamma ray shield of a non-radioactive heavy metal surrounding the second moderator region.

14. The apparatus of claim 13 and wherein:

the radius from the center of the first core region to the outside of the gamma ray shield is about one meter.

15. A nuclear fission reactor having a core as a source of fast and epithermal neutrons, the core having a fuel therein having a macroscopic inelastic neutron scattering cross section that is characteristic of uranium metal fuel;

material around the fuel for strong inelastic down-scattering of fast neutrons;

adjustable moderator with 1/v-absorber combination to optimize epithermal neutron spectra for different tumors;

shielding media surrounding the reactor;

a plurality of neutron transmission passageways extending outward through said media; and

treatment stations at the ends of the passageways outside the media.

16. The apparatus of claim 15 and wherein:

the core has a center and has nuclear fuel arranged therein such that there is decreasing fissile material concentration at increasing distances from the center.

17. The apparatus of claim 16 and wherein:

the core is multi-regional including a first region at the center, a second region around the first region and a third region around the second region,

the three regions having decreasing enrichment from the highest at the first region to the lowest at the third region.

18. The apparatus of claim 17 and wherein:

the first region comprises uranium enriched to about 20% U-235,

the second region comprises uranium enriched to about 4% U-235; and

the third region comprises a heavy metal.

19. The apparatus of claim 16 and wherein:

the moderator with absorber combination is in the reactor and includes segmented rings of liquids around the core and arranged for selectively changing the mean epithermal energy of neutrons transmitted through the passageways.

20. The apparatus of claim 19 and wherein:

the liquid in one of the rings is different from the liquid in another of the rings.

21. The apparatus of claim 20 and wherein:

the rings are sectored about the center, the liquids in the rings of one sector being separate from the liquids in the rings of another sector.

22. A method of treating a plurality of subjects with neutron-capture therapy comprising the steps of:

locating individual subjects in plurality of treatment stations around a nuclear reactor having a nuclear fuel core;

exposing the subjects to epithermal neutron emission from a fast nuclear reactor core surrounded by metal and liquid moderator regions, after narrowing the spread of the neutron energy spectrum by inelastic and elastic scattering, the elastic scattering especially in moderators combined with 1/v absorption in moderators around the metal regions.

23. The method of claim 22 and further comprising the steps of:

narrowing the spread of the neutron energy spectrum by absorbing neutrons in moderator liquid rings around the core, and

using different liquid compositions in at least two of the moderator rings.

24. The method of claim 22 and further comprising the step of:

absorbing neutrons in at least one moderator liquid ring around the core.

25. The method of claim 24 and further comprising the step of:

locating the subjects at a distance between one and two meters from the core.

26. The method of claim 24 and further comprising the step of:

dividing the moderator liquid ring into sectors, and

using a moderator liquid composition in one sector that is different from the composition in at least one other sector.

27. The method of claim 24 and further comprising the step of:

providing 1/v neutron absorbing material in the ring partly as solid and partly as liquid.