Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions

Abstract

Full tungsten poloidal and mushroom limiters were tested in series of experiments with disruptions in the T-10 tokamak. Significant melting, formation of small craters and erosion of the tungsten limiter have been observed after ∼400 discharges with disruption. A theoretical description of the tungsten erosion at disruption in tokamak plasma is presented. The proposed model was verified by comparison with experimental observations in the T-10. The results are used for the erosion prediction of the ITER tungsten divertor. Keywords: Fusion reactor materials, Tungsten, Combining heat and particle load, Disruption, Tokamak, ITER