Classical resistivity in a post-thermal quench disrupting plasma

Confirmation of the common assumption that post-thermal quench plasma resistivities are classical is a key requirement to enable prediction of peak halo current amplitudes expected in mitigated tokamak disruptions. Using numerical simulations and direct plasma measurements, the present work demonstrates that resistivities of core and halo plasmas are indeed classical following a disruption thermal quench. Simulations of core and halo current evolution in tokamak disruptions mitigated by massive He gas puff are performed which make use of direct measurements of post-thermal quench plasma electron temperature and Zeff.