 n/nGr of 0.0, and a peak divertor heat flux of 00.0 MW/m² . The conservative configuration assumes a dual-coolant lead lithium blanket concept with reduced activation ferritic martensitic steel structural material and helium coolant, achieving a thermal conversion efficiency of 00%. The plasma has a major radius of 0.00 m, a toroidal field of 0.00 T, a q₉₅ of 0.0, aᵦtotalN of 0.0, an H₉₈ of 0.00, an n/nGr of 0.0, and a peak divertor heat flux of 00 MW/m² . The divertor heat flux treatment with a narrow power scrape off width has driven the plasmas to larger major radius. Edge and divertor plasma simulations are targeting a basis for high radiated power fraction in the divertor, which is necessary for solutions to keep the peak heat flux in the range 00 to 00 MW/m² . Combinations of the advanced and conservative approaches show intermediate sizes. A new systems code using a database approach has been used and shows that the operating point is really an operating zone with some range of plasma and engineering parameters and very similar costs of electricity. Other papers in this issue provide more detailed discussion of the work summarized here.