Bulletin of the American Physical Society
60th Annual Meeting of the APS Division of Plasma Physics
Volume 63, Number 11
Monday–Friday, November 5–9, 2018; Portland, Oregon
Session CP11: Poster Session II: Basic Plasma Physics; Boundary, PMI, Proto-MPEX; International Tokamaks; Turbulence and Transport; Other Configurations; Z-pinch, Dense Plasma Focus and MagLIF (2:00pm-5:00pm)
Monday, November 5, 2018
OCC
Room: Exhibit Hall A1&A
Abstract ID: BAPS.2018.DPP.CP11.78
Abstract: CP11.00078 : Simulation of Tungsten Erosion and Migration in the ITER Divertor as Part of an Integrated Model for PSI
Presenter:
Tim Younkin
(Oak Ridge National Lab, University of Tennessee)
Authors:
Tim Younkin
(Oak Ridge National Lab, University of Tennessee)
John Canik
(Oak Ridge National Lab)
Mark R Cianciosa
(Oak Ridge National Lab)
Philip C Roth
(Oak Ridge National Lab)
Ane Lasa
(University of Tennessee-Knoxville)
Davide Curreli
(Univ of Illinois - Urbana)
Jon T Drobny
(Univ of Illinois - Urbana)
Sophie Blondel
(University of Tennessee-Knoxville)
Brian Wirth
(University of Tennessee)
Wael Elwasif
(ORNL)
David L Green
(Oak Ridge National Lab)
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)
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2018.DPP.CP11.78
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