Integrated modeling of ITER scenarious with carbon and tungsten walls

Abstract The COREDIV code describing self-consistently plasma and impurity transport in the tokamak core and boundary regions is applied to simulate ITER discharges with carbon and tungsten divertors. Simulations show in the case of the standard inductive scenario, that for both materials it is possible to achieve discharges with Q > 10. The fusion performance is better with tungsten divertor due to smaller plasma dilution. However, with tungsten target the seeding is necessary to reduce the heat load to divertor plates whereas in the case of carbon, seeding might be avoided. For the steady state scenario the fusion performance is very bad ( Q ∼ 3) with carbon divertor and the neon seeding does not improve the situation. In the case of tungsten divertor, the discharge performance is better due to lower plasma contamination and the Q values close to 5–6 can be achieved.