Simulation of Tungsten Erosion and Migration in the ITER Divertor as Part of an Integrated Model for PSI
POSTER
Abstract
A new simulation capability has been developed to simulate the coupled interaction of the plasma and surfaces in fusion devices. The integrated model includes a wide range of phenomena, including models for a) the scrape-off layer plasma including fuel ions and extrinsic impurities (using SOLPS[1]), b) transport and redeposition of eroded wall material (using the newly developed Monte Carlo code GITR[2]), c) the implantation of plasma ions into the material and subsequent wall erosion (using F-TRIDYN,[3]), and d) the dynamics of the subsurface. These components have been combined to predict the evolution of surface morphology, recycling and retention, and the impact of erosion and redeposition on these processes. After benchmarking against PISCES experiments, we have now applied this model to make predictions to the ITER divertor. Predictions for standard and helium operations, and for a partially and completely detached divertor, will be presented. Modeling results presented focus on the input data for the impurity transport simulation and their impact on impurity migration in the ITER divertor.
[1] R. Schneider et al, Contrib. Plasma Phys. 46 (2006) 3.
[2] GITR Github repository, https://github.com/ORNL-Fusion/GITR
[3] J. Drobny, J. Nucl. Mat. 494 278-283 (2017)
Presenters
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Tim Younkin
- University of Tennessee
- Oak Ridge National Lab
- Oak Ridge National Lab, University of Tennessee
- University of Tennessee-Knoxville