| Summary: | An inventive method was applied to determine the minimum major radius, <i>R</i><sub>0</sub>, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses were carried out over ranges of system parameters to find an optimum build of a tokamak fusion reactor at minimum cost. The impact of a wide range of physics parameters and advanced engineering elements on costs were also addressed. When a central solenoid was used to ramp up a plasma current, design solutions with a cost of electricity (COE) between 109 and 140 mills/kWh, direct capital cost between 5000 and 6000 M/USD, and net electric power, <i>P<sub>e</sub></i> between 1000 and 1600 MW could be found with a minimum <i>R</i><sub>0</sub> between 6.0 and 7.0 m, and fusion power, <i>P<sub>fusion</sub></i> between 2000 and 2800 MW. When the plasma current was driven by a non-inductive external system, the system size and costs could be reduced further; a COE between 98 and 130 mills/kWh, direct capital cost between 4000 and 5000 M$, and <i>P<sub>e</sub></i> between 1000 and 1420 MW could be found with a minimum <i>R</i><sub>0</sub> between 5.1 and 6.7 m, and <i>P<sub>fusion</sub></i> between 2000 and 2650 MW.
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