In the present scenario for the development of magnetic confinement fusion, the availability of tritium needed to fuel a D-T burning plasma in order to generate 14 MeV neutrons for material and system component testing is not being fully addressed. An alternate approach based on the in situ generation of tritium in a driven D-D reacting plasma is proposed. The feasibility of this approach to attain 14 MeV neutron flux levels comparable with D-T fueled burning plasma from a modest beta, first generation fusion power reactor can be established from known results. A staged scenario, is described in which tritium bred from developmental blankets is used to fuel the system to incrementally raise the neutron wall loading to simulate more advanced fusion reactors.