Abstract
The Fast Mixed-Spectrum Reactor (FMSR) concept has been proposed as a means of alleviating certain non-proliferation concerns relating to civilian nuclear power. In particular, the concept is envisioned as operating on a natural uranium feed (after initial startup), thus eliminating the need for fuel reprocessing. The primary basis for the concept involves the production, in situ, of the fissile material required for criticality from the fertile feed material. The results of a preliminary study directed at assessing the neutronic feasibility of the concept are reported.
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