Neutron Source for Neutron Capture Therapy

• US 20120330084A1
• Filed: 06/25/2012
• Published: 12/27/2012
• Est. Priority Date: 06/27/2011
• Status: Abandoned Application

• Current Assignee: Adelphi Technology Incorporated
• Original Assignee: Adelphi Technology Incorporated
• Inventors: Piestrup, Melvin Arthur, Pantell, Richard Harris, Gary, Charles Kevin
• Application Number:
  US13/532,447
• Publication Number:
  US 20120330084A1
• Time in Patent Office: Days
• US Class Current: 600/1
• CPC Class Codes: A61N 2005/109 Neutrons
• CPC Class Codes: A61N 2005/1094 Shielding, protecting against radiation
• 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 5/1077 Beam delivery systems
• CPC Class Codes: G21G 4/02 Neutron sources

Abstract

A therapy apparatus for producing thermal neutrons at a tumor site in a patient has a plurality of fast neutron sources surrounding a moderator, a fast neutron reflecting media around the fast neutron sources, a gamma-ray and neutron shielding media surrounding the fast neutron reflecting media, and a patient chamber positioned inside the moderator. The fast neutron sources are positioned around the moderator to maximize and direct the neutron flux to said tumor site.

Claims

1. A therapy apparatus for producing thermal neutrons at a tumor site in a patient comprising:

a plurality of fast neutron sources surrounding a moderator;

a fast neutron reflecting media around the fast neutron sources;

a gamma-ray and neutron shielding media surrounding the fast neutron reflecting media; and

a patient chamber positioned inside the moderator;

wherein the fast neutron sources are positioned around the moderator to maximize and direct the neutron flux to said tumor site.

2. The therapy apparatus according to claim 1 wherein the moderator maximizes the neutron flux, delivers a uniform dose and a high and uniform therapeutic ratio across the cancer site.

3. The therapy apparatus according to claim 1 wherein the patient chamber'"'"'s position and material of the moderator are selected to produce the maximum, uniform thermal neutron flux and uniform therapeutic ratio at the said tumor sites.

4. The therapy apparatus according to claim 1 wherein the fast neutron sources are positioned at a fixed radius and equally spaced in a circle around the moderator.

5. The therapy apparatus according to claim 1 wherein the fast neutron sources are moveable and positioned to maximize the neutron flux at the cancer site.

6. The therapy apparatus according to claim 1 wherein said fast neutron sources are moveable and are positioned to maximize the neutron flux at the cancer site, to deliver a uniform dose across the cancer site greater than 1 Gy per session with a 10% or less variation, and to deliver a therapeutic ratio at the cancer site greater than 2, and with a uniformity across the cancer site of 10% or less variation.

7. A therapy apparatus according to claim 1 wherein said moderator is cylindrical in shape.

8. A therapy apparatus according to claim 1 wherein the moderator is hemispherical in shape.

9. The therapy apparatus according to claim 1 wherein the moderator is ellipsoidal in shape.

10. A therapy apparatus for producing thermal neutrons at tumor sites in a patient comprising:

a plurality of fast neutron sources;

a moderator disposed inside the fast neutron sources;

a patient chamber disposed inside and center of the moderator; and

,

a neutron reflector and shielding apparatus disposed around the fast neutron generating target.

11. A therapy apparatus for producing thermal neutrons at a tumor site in a patient comprising:

a plurality of ion sources;

a cylindrical electron shield disposed coaxially inside the said ion sources;

a cylindrical fast-neutron generating target disposed coaxially inside said electron shield that includes an ion entrance aperture disposed to have ions emitted from the ion source impact a fast-neutron-generating target;

a cylindrical moderator disposed coaxially inside the said cylindrical fast-neutron-generating target;

a patient chamber disposed coaxially inside said cylindrical moderator; and

a neutron reflection and shielding means disposed coaxially around said ion beam sources.