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 GM9: Mini-Conference on Plasma–Material Interactions in Fusion Devices: ITER and Beyond. I. Integrated PMI Modeling and Analysis
9:30 AM–12:20 PM,
Tuesday, November 6, 2018
OCC
Room: C123
Chair: IIon Joseph, Lawrence Livermore National Laboratory
Abstract ID: BAPS.2018.DPP.GM9.2
Abstract: GM9.00002 : Status of integrated simulation of PFC surface evolution within the PSI-SciDAC project*
9:55 AM–10:20 AM
Presenter:
John Canik
(Oak Ridge National Lab)
Authors:
John Canik
(Oak Ridge National Lab)
Ane Lasa
(University of Tennessee-Knoxville)
Sophie Blondel
(University of Tennessee-Knoxville)
Mark R Cianciosa
(Oak Ridge National Lab)
Davide Curreli
(Univ of Illinois - Urbana)
Jon T Drobny
(Univ of Illinois - Urbana)
Wael Elwasif
(Oak Ridge National Lab)
David L Green
(Oak Ridge National Lab)
Philip C Roth
(Oak Ridge National Lab)
Tim Younkin
(University of Tennessee-Knoxville)
Brian Wirth
(University of Tennessee-Knoxville)
Russ Doerner
(Univ of California, San Diego)
Daisuke Nishijima
(Univ of California - San Diego)
Matthew Baldwin
(Univ of California - San Diego)
A new simulation capability is being developed within the PSI-SciDAC project to simulate the long-term evolution of plasma-exposed surfaces. 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) sheath physics (using the hPIC code), c) transport and redeposition of eroded wall material (using the new Monte Carlo code GITR), d) implantation of ions into the wall and subsequent erosion (using F-TRIDYN, an extension of TRIDYN [2]), and e) dynamics of the subsurface (Xolotl, a new continuum cluster dynamics code). 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, assuming steady-state conditions and without feedback on the background plasma. After benchmarking against PISCES experiments, we have now applied this model to make predictions for the ITER divertor. Predictions for standard and helium operations, and for a partially and completely detached divertor, will be presented. [1] R. Schneider et al, Contrib. Plasma Phys. 46 (2006) 3. [1] W. Miller et al, Comp. Phys. Comm. 51 (1988) 355.
*Research supported by US DOE under DE-AC05-00OR22725
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2018.DPP.GM9.2
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