Description
The COMPASS Upgrade is a medium size tokamak ($R = 0.89~\mathrm{m}$, $a = 0.27~\mathrm{m}$) with a high magnetic field ($B = 5~\mathrm{T}$), high plasma density ($n_e \le 3 \times 10^{20}~\mathrm{m}^{-3}$), high plasma current ($I_p = 2~\mathrm{MA}$), and with a reactor relevant hot wall (up to $500~^{\circ}\mathrm{C}$). It is currently under construction at IPP CAS with first plasma planned for 2030. Accessibility to high density operation and flexibility for exploring different plasma exhaust capabilities enables COMPASS-U to explore questions regarding the plasma exhaust and alternative confinement modes (QCE, EDA H-mode, XPR, I-mode, etc.) at ITER and future reactor-relevant fusion devices. We employ the SOLPS-ITER code to model the edge plasma. The SOLPS-ITER code is a combination of a multi-fluid plasma transport code B2.5 and a kinetic Monte Carlo neutrals transport code EIRENE. To address the issue with the radially constrained mesh extent we use the Wide Grids version of the code. Contrary to our previous simulations with Narrow Grid version of SOLPS-ITER, we see significantly higher divertor and reduced wall heat loads. \par
Results of SOLPS-ITER simulations for the high-performance scenario (#5400) are presented. Simulations performed with kinetic neutral module (EIRENE), without drifts and seeded impurity. A general challenge in predictive simulations for future machines and new scenarios is the presence of many unknowns and high uncertainty. Reduced, integrated modeling can provide estimates of general plasma conditions to higher-fidelity models; in turn, more complex modeling can be used to validate or calibrate these simpler models. This contribution details the integrated workflow used and provides a cross-validation of the SOLPS-ITER simulations against other models and predictions.