Patent ID: 7796720
Filing Date: 2010-09-14
Classification: G21G

Abstract:
1. A method of producing a useful short lived radioisotope for medical or industrial applications from a first target isotope, the method comprising the steps of: providing a first buffer region around a neutron source for providing a first reduction in neutron energy by inelastic scattering; providing an activation region around the first buffer region, said activation region being made of heavy elements of lead and/or bismuth; distributing a material containing said first target isotope throughout the whole volume of the activation region, the inner buffer region and the neutron source being devoid of said first target isotope; activating the neutron source to emit a neutron flux such that neutrons of said neutron flux are captured by the first target isotope to produce said useful short-lived radio-isotope for medical or industrial applications; and recovering said useful short-lived radioisotope from the exposed material for use in medical or industrial applications; wherein multiple elastic collisions between the neutrons in the neutron flux and the heavy elements in the activation region result in an enhanced neutron flux in the activation region; and a rate of progressive decrease in neutron energy such that neutron capture efficiency in said first target isotope is enhanced by resonance neutron capture.