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 PP11: Poster Session VI: Relativistic Laser Plasma Interaction and Beam Physics; Boundary; MHD and Stability, Transients; FRC; Dusty Plasmas; Basic Studies; Computational and Diagnostic Methods (2:00pm-5:00pm)
Wednesday, November 7, 2018
OCC
Room: Exhibit Hall A1&A
Abstract ID: BAPS.2018.DPP.PP11.43
Abstract: PP11.00043 : Real-time model-based wall heat flux estimation for ITER
Presenter:
Himank Anand
(ITER Organization)
Authors:
Himank Anand
(ITER Organization)
Richard A Pitts
(ITER Organization)
Peter C de Vries
(ITER Organization)
Joseph A Snipes
(ITER Organization)
Isabel Nunes
(ITER Organization)
Luca Zabeo
(ITER Organization)
Cristian Galperti
(EPFL-SPC)
Federico Nespoli
(Aix Marseille University)
Roberto Maurizio
(EPFL Lausanne)
Stefano Coda
(EPFL - Lausanne)
Benoit Labit
(EPFL-Lausanne)
Holger Reimerdes
(EPFL-Lausanne)
A real-time (RT) first wall (FW) heat load control system will be required at a very early stage of ITER plasma operations. A Matlab/Simulink architecture containing a 2D, control oriented model, based on RT equilibrium reconstruction has been successfully implemented for the ITER Plasma Control System (PCS). Integration of the real 3D nature of the ITER PFCs into the algorithm is performed by offline determination of the heat load distribution on a full 3D poloidal sector using a new magnetic field line tracing utility, SMITER, permitting import and appropriate meshing of CAD descriptions of the FW geometry. Weighting factors are then derived with which to correct the peak heat fluxes obtained from the 2D model for implementation into the heat flux control algorithm. A detailed study of the ramp-up phase in a limiter configuration has been performed using the DINA code to generate magnetic equilibria and including a plasma current scaled, double exponential radial profile of parallel heat flux. The approach proposed for ITER has been experimentally demonstrated and benchmarked against off-line measurements from infra-red (IR) camera diagnostics for both limiter and diverted plasma configurations on the TCV tokamak.
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2018.DPP.PP11.43
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