The basic fusion ignition experiment IGNITEX can achieve plasma ignition through the use of high toroidal fields (20 T) and ohmic heating. The experiment will operate in a pulsed tokamak mode with one discharge every two hours. The single-turn-coil system will be driven by homopolar generators and will be cooled by a liquid nitrogen bath. The experimental program will stretch over a three year period with the first D-T fueled discharges taking place after about 19 months of operation. Hands-on maintenance is possible both inside and outside the primary shielding due to the low activation levels of the experiment. This low activation is because of the almost complete coverage of the vacuum vessel by the thick copper magnetic coil system and the single-turn coil design which does not require the usual high activation laminate materials. IGNITEX systems are designed to provide high reliability and simplicity to extend machine availability in the fusion ignition regimes.