Abstract
The results of experiments on powerful plasma stream-surface interaction in conditions of heat loads typical for current disruptions in reactor-tokamak ITER are presented here. The long pulse powerful plasma streams are generated with quasi-steady-state plasma accelerator QSPA Kh-50. The morphology of surfaces of tungsten and graphite, as well as surface of combined tungsten-graphite targets exposed to powerful plasma streams is analyzed. Some erosion properties of these materials are presented and compared with results of numerical simulations.
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References
G. Federici at al.: Plasma Phys. Control. Fusion 45 (2003) 1523.
A. Loarte et al.: Plasma Phys. Control. Fusion 45 (2003) 1549.
V. I. Tereshin et al.: Plasma Phys. Control. Fusion 37 (1995) A177–A190.
V. I. Tereshin et al.: Brazilian Journal of Physics 32/1 (2002) 165–171.
V. I. Tereshin et al.: J. Nucl. Mater. 313–316 (2003) 685–689.
I. E. Garkusha: J. Nucl. Mater. 337–339 (2005) 707–711.
N. Arkhipov et al.: Fusion technology. 32 (1997), 45–74.
F. Scaffidi-Argentina et al.: J. Nucl. Mater., 283–287 (2000) 1111–1115.
H. Wuerz, et al.: J. Nucl. Mater. 290–293 (2001) 1138.
Y. Hatano, et al.: J. Nucl. Mater. 307–311 (2002) 1339.
W. Espe: Werkstoffkunde der Hochvakuumtechnik, Band 1, Metalle und metallisch leitende Werstoffe, VEB Deutscher Verlag der Wissenschaften, Berlin, 1959.
M. I. Guseva et al.: Plasma Devices and Operations 11/3 (2003) 141–153.
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Tereshin, V.I., Bandura, A.N., Byrka, O.V. et al. Simulation of iter transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator. Czech J Phys 56 (Suppl 2), B162–B169 (2006). https://doi.org/10.1007/s10582-006-0193-4
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DOI: https://doi.org/10.1007/s10582-006-0193-4