Research on molten salt reactors in the 60's culminated in a
reference design for a 1000 MW breeder reactor using circulating fuel salt moderated by graphite. A secondary salt heat transfer loop circulated to a rack of high pressure steam generators feeding a steam turbine. Onsite fuel processing was planned. Primary outstanding questions at the conclusion of the study centered around reprocessing, tritium handling, remote maintenance, and long term neutron irradiation of structural materials (at the astounding rate of around 2 1/2 quadrillion zoomies per second per square inch for 30 years). Corrosion was pretty much a so!ved problem by then, although erosion remained a concern in high velocity locations.