期刊
FUSION ENGINEERING AND DESIGN
卷 124, 期 -, 页码 401-404出版社
ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2017.02.048
关键词
TOKES; Numeric simulations; Plasma shield; Experimental code validation
资金
- ITER Organization [ITER/CT/14/4300000998]
Measurements of tungsten (W) plasma shield dynamics have been performed in the 2MK-200 facility under ITER relevant disruptive plasma heat flux densities of similar to 100 GW/m(2). Plasma temperature profiles at two time instants and time dependent electron density profiles are available from these experiments. These data have been used to validate TOKES code simulations of the W plasma shield which is computed to form in front of the ITER W divertor targets during disruptions. The experimental and simulated temperature profiles are in a good agreement for the measurement points at distances of 1-5 cm from the target. An important feature of the W plasma shield seen in the code simulations is the sharp electron temperature drop very close to the target. This region is not resolved in the 2MK-200 facility because of unacceptably low signal/noise ratio. Further experiments in a new, larger plasma gun are planned for experimental validation of this feature. (C) 2017 Elsevier B.V. All rights reserved.
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