> While a well-designed control system can effectively stabilize a tokamak, failures or unforeseen magnetohydrodynamic (MHD) instabilities can still trigger plasma disruptions. An effective mitigation technique involves injecting impurities into the plasma, causing a quick radiation of most of its thermal energy (thermal quench, TQ). The rise in plasma’s electrical resistance at the end of the TQ results in the formation of large toroidal electric fields, which accelerate the electrons to relativistic velocities (runaway electrons, REs). As they avalanche, potentially carrying a large fraction of the pre-disruption plasma current, REs can locally damage the first wall by applying thermal loads of several tens of MJ/m2, possibly leading to deep melting. Our investigation focuses on examining the generation of REs following a mitigated disruption in the specific setting of the Divertor Tokamak Test (DTT) facility [^1]. Axisymmetric simulations concern both the “Day 0” scenario and “Full Power” scenario, which have a nominal plasma current of 2 MA and 5.5 MA respectively. We exploit the RE fluid model of the non-linear MHD code JOREK [^2], coupled with the vacuum-field code STARWALL [^3][^4]. A simplified approach is adopted here, by performing an artificial thermal quench (ATQ) of the plasma and focusing on the REs generation only. A scan in the impurity content is analyzed to evaluate how sensitive the REs generation is to such values. Eventually, this study will conduce to prediction of the heat load caused by RE beams on the plasma-facing components of DTT, to aid in its design of effective disruption mitigation strategies. [^1]: R. Martone, et al, ENEA, Frascati, Italy, P. 261, ISBN 9788882863784 (2019) [^2]: M. Hoelzl et al, Nuclear Fusion 61, 065001 (2021) [^3]: P. Merkel et al, IAEA Fusion Energy Conference TH/P3-8 (2006) [^4]: M. Hoelzl et al, Journal of Physics. Conference Series 401, 012010 (2012)