Neutron Source for Neutron Capture Therapy

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.

Description

CROSS REFERENCED TO RELATED APPLICATIONS[0001]This application is a non-provisional application of provisional patent application Ser. No. 61 / 571,406 filed Jun. 27, 2011 by the present inventors.BACKGROUND OF THE INVENTION[0002]1. Field of the Invention[0003]This invention is in the technical area of apparatus and methods for generating neutrons for cancer therapy.[0004]2. Description of Related Art[0005]Thermal neutrons have been used for cancer therapy for the destruction of cancer tumors. These neutrons interact with boron-10 that has been placed at the cancer site. The neutrons interact with the boron to produce fission events whereby alpha particles and lithium nuclei are created. These massive ionized particles are then released, destroying the chemical bonds of nearby cancer tumor cells. At present the neutrons created in a reactor or accelerator pass through a moderator, which shapes the neutron energy spectrum suitable for Boron Neutron Capture Therapy (BNCT) treatment. Whi...

AI Technical Summary

Benefits of technology

[0022]The invention in one embodiment is a neutron irradiation system that permits boron neutron capture therapy (BNCT) for cancer. It does this by delivering a uniform dose of thermal neutrons across the body organ (e.g. brain, liver or other organ) with a higher dose of neutrons to the tumor site over that of the healthy tissue and skin. This is accomplished with a unique neutron source that can be conveniently situated in a clinic, an outpatient facility, or a research laboratory. In one embodiment the neutron irradiation system uses the DD reaction at reasonable acceleration power levels and is relatively inexpensive and compact enough to be used in hospitals. The invention in one embodiment consists of multiple fast neutron sources (N≧2) arranged around a hemispherical or cylindrical moderator made of aluminum fluoride, heavy water or other efficient moderating materials. The fast-neutron source geometry is matched with the moderator and the patient's brain or body in a synergistic fashion to produce a uniform thermal neutron dose and therapeutic ratio across the brain or body part. In this embodiment the required fast neutron yield is almost two orders of magnitude smaller than that required from the prior art that uses a planar geometry. This permits using a safe DD reaction and lower electrical power and is critical for the development of a clinic-based system.

Problems solved by technology

The release of this energy destroys surrounding cancer cells.

GBM is nearly always fatal and has no known effective treatment.

Conventional radiation treatment is usually too toxic to be of use against GBM.

Primary and metastatic liver cancers are usually fatal, especially after resection of multiple individual tumors.

The response rate for nonresectable hepatocellular carcinoma to traditional radiation treatment or chemotherapy is also very poor.

BNCT has been tested using either nuclear reactors or accelerators, which are not practical or affordable for most clinical settings.

Reactors also do not produce an ideal neutron spectrum and are contaminated with y-radiation.

Unfortunately, since the neutrons are entering from one side of the head, the planar neutron irradiation system leads to a high surface or skin dosage and a decreasing neutron dose deeper into the brain.

This is an inefficient process requiring a large amount of fast neutrons to be produced in order to produce enough thermal neutrons for reasonable therapy or treatment times (e.g. 30 min).

The use of tritium has a whole host of safety and maintenance problems.

Tritium gas is radioactive and extremely difficult to eliminate once it gets on to a surface.

The generator head can not be easily maintained and usually its lifetime is limited to less than 2000 hours.

This reduces the possible use of this generator for clinical operation since the number of patients who could be treated would be small before the generator head would need replacement.

The downside for the DD fusion reaction is that high acceleration powers are required to achieve the desired neutron yield required by prior art methods.

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