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Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions
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
Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions
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
Tungsten melting and erosion under plasma heat load in tokamak discharges with disruptions
V.P. Budaev (author) / Yu.V. Martynenko (author) / S.A. Grashin (author) / R.N. Giniyatulin (author) / I.I. Arkhipov (author) / A.V. Karpov (author) / P.V. Savrukhin (author) / E.A. Shestakov (author) / R.Yu. Solomatin (author) / L.B. Begrambekov (author)
2017
Article (Journal)
Electronic Resource
Unknown
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