High-flux electronically generated thermal neutron source for radiographic applications

An innovative approach to generating a high thermal neutron flux (108 n/cm2/s) at a distance of 1 m from the source via D-T nuclear fusion reactions is proposed. By making use of Inertial Electrostatic Confinement (IEC) technology, which creates reactions between a re-circulating ion beam and a gas target, the limitations on lifetime of fusion sources that use solid targets can be overcome, while still possessing the advantages of being electronic. Additionally, substantial improvements in neutron moderator efficiency are proposed that can relax the requirements on total output for isotropic sources, improving efficiency and decreasing leakage radiation. Preliminary studies using the MCNPX code indicate that creative moderator designs can increase thermal neutron efficiency by over 50 times that from existing moderators. The goal of this proposal is to increase IEC neutron production rates by a factor of 4 in phase I, and a factor of 5 in phase II to reach a final rate of > 1013 n/s. Furthermore, moderator efficiency will increase by an additional factor of 4 in phase 1, and 20 in phase 2. These enhancements will allow the thermal flux on a target to be 2*106 n/cm2/s after phase I, and 1*108 n/cm2/s after phase II.