A reduced boundary plasma transport model workflow for Core-Edge-SOL (CESOL) integrated modeling for fast analysis of compact tokamak design points.

Sophisticated tools like SOLPS are the vital foundation for high fidelity calculations of plasma transport properties in the scrape-off layer (SOL) of tokamak plasmas. However, their applicability in reactor design is currently limited by computational time and resources. Even if reduced model predictions for the SOL are not yet validated in a fusion pilot plant regime, the ability to rapidly design the integrated first wall and divertor systems in the presence of uncertainty allows progress in assessing feasibility of engineering requirements. We present a 1D SOL equilibrium transport code, C1, as a low fidelity SOL piece of the CESOL workflow that aims to provide fast, robust calculations of ion, neutral, and energy fluxes through the pedestal, SOL, and to the divertor to optimize for e.g., heat flux to the divertor. Initial work has extended the C1 solver to use GTNEUT as a neutral species solver, include radial dynamics, and solve the fluid ion continuity & parallel momentum and ion & electron temperature equations on a more realistic spatial grid based on geqdsk data. This self-consistent calculation of the separatrix density and temperatures is being used in large parameter scans for the aspect ratio optimization of a compact advanced tokamak. Future work aims to continue by adding impurity models, read and include ADAS cross section data, and finally benchmark C1 against SOLPS.