Modeling plasma-lithium wall interactions in LTX-β with SOLEDGE3X-EIRENE

We present the first results of SOLEDGE3X-EIRENE modeling plasma radiation in the Lithium Tokamak Experiment-β (LTX). By setting up the model using Thomson scattering measurements, we have determined the SOLEDGE3X input parameters, such as edge density and temperature. The simulation uses pure hydrogen (H). Neutrals are modelled kinetically with EIRENE. The mean-field transport coefficients for particles cross-field diffusion D_⊥ and viscosity ν_⊥ were such that D_⊥ = ν_⊥= 0.2 m² s^-1 , and cross-field heat conductivity for ions and electrons were χ_i = χ_e = 0.2 m² s^-1 . For this study, we set the density and temperature at the code edge interface at the inner computational boundary. This simulation domain is, therefore, technically fueled from the core to mainly the density and temperature, and a pump with an an albedo of 0.95 is implemented in the lower side of the vessel. These simulation results will be compared with the experimental electron density and temperature profiles at the boundary to validate their accuracy. A qualitative analysis of synthetic diagnostic signals for impurities will also be presented, contributing to a deeper understanding of edge physics in LTX-β. Furthermore, we examine the impurity migration of lithium using the hydrogen plasma results from SOLEDGE3X-EIRENE, employing these results in the global impurity transport code SPARTA-PMI to determine the charge state abundances and spatial distribution of lithium. The synthetic data will be compared against experimental measurements to validate the simulations and provide insights into lithium behavior. We will also look at shots with both liquid and solid lithium surfaces to enhance the comprehensiveness of our study.