Neutron Transport and Activation Analysis for the IGNITEX Device

IGNITEX is a tokamak experimental device that is designed to study alpha particle heating and ignition in D-T plasmas. To make possible a small, simple, and low cost experiment, IGNITEX will employ Ohmic heating to reach ignition and very high magnetic fields from an unconventional single turn toroidal field coil. As the initial step in the safety analysis for IGNITEX, radiation transport through the device and its surrounding concrete shield has been calculated using ANISN. Activation of the IGNITEX structure was computed using REAC2. The inventory of radioactive material produced by operation of IGNITEX is not expected to present any significant waste disposal or ventilation problems.