Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions
oleh: V.P. Budaev, Yu.V. Martynenko, S.A. Grashin, R.N. Giniyatulin, I.I. Arkhipov, A.V. Karpov, P.V. Savrukhin, E.A. Shestakov, R.Yu. Solomatin, L.B. Begrambekov, N.E. Belova, S.D. Fedorovich, L.N. Khimchenko, V.M. Safronov
| Format: | Article |
|---|---|
| Diterbitkan: | Elsevier 2017-08-01 |
Deskripsi
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