Simulation of tokamak armour erosion and plasma contamination at intense transient heat fluxes in ITER

I.S. Landman^a, B.N. Bazylev^a, I.E. Garkusha^b, A. Loarte^c, S.E. Pestchanyi^a,

V.M. Safronov^d

^aForschungszentrum Karlsruhe, Institute for Pulsed Power and Microwave Technology, P. B. 3640, 76021 Karlsruhe, Germany

^bInstitute of Plasma Physics of the National Science Centre “Kharkov Institute of Physics and Technology”, 61108, Kharkov, Akademicheskaya St. 1, Ukraine

^cEFDA-Close Support Unit, Garching, Max-Planck Institute für Plasmaphysik, D-85748, Garching bei München, Germany

^dState Research Centre of Russian Federation Troitsk Institute for Innovation and Fusion Research, 142190, Troitsk, Moscow region, Russia

Abstract

For ITER, the potential material damage of plasma facing tungsten-, CFC-, or beryllium components during transient processes such as ELMs or mitigated disruptions are simulated numerically using the MHD code FOREV-2D and the melt motion code MEMOS-1.5D for a heat deposition in the range of 0.5 - 3 MJ/m2 on the time scale of 0.1 - 1 ms. Such loads can cause a significant evaporation at the target surface and a contamination of the SOL by expanding material impurities. Results are presented on carbon plasma expansion in toroidal geometry and on radiation fluxes from the impurities obtained with FOREV-2D. The validation of MEMOS-1.5D against the plasma gun tokamak simulators MK-200UG and QSPA-Kh50 by the tungsten melting threshold is described. Simulations with MEMOS-1.5D for a beryllium first wall that provide important details about the melt motion dynamics and typical features of the damage are reported.