Journal ArticleDOI
Development of the ITER baseline inductive scenario
T.A. Casper,Y. Gribov,A. Kavin,V.E. Lukash,R.R. Khayrutdinov,H. Fujieda,C.E. Kessel,Iter Domestic Agencies +7 more
TLDR
In this paper, the authors present new results of transport simulations fully consistent with the final ITER design that remain within allowed limits for the coil system and power supplies, and increase their confidence in meeting the challenges of the ITER program.Abstract:
Sustainment of Q ~ 10 operation with a fusion power of ~500 MW for several hundred seconds is a key mission goal of the ITER Project. Past calculations and simulations predict that these conditions can be produced in high-confinement mode operation (H-mode) at 15 MA relying on only inductive current drive. Earlier development of 15 MA baseline inductive plasma scenarios provided a focal point for the ITER Design Review conducted in 2007–2008. In the intervening period, detailed predictive simulations, supported by experimental demonstrations in existing tokamaks, allow us to assemble an end-to-end specification of this scenario consistent with the final design of the ITER device. Simulations have encompassed plasma initiation, current ramp-up, plasma burn and current ramp-down, and have included density profiles and thermal transport models producing temperature profiles consistent with edge pedestal conditions present in current fusion experiments. These quasi-stationary conditions are maintained due to the presence of edge-localized modes that limit the edge pressure. High temperatures and densities in the pedestal region produce significant edge bootstrap current that must be considered in modelling of feedback control of shape and vertical stability. In this paper we present new results of transport simulations fully consistent with the final ITER design that remain within allowed limits for the coil system and power supplies. These self-consistent simulations increase our confidence in meeting the challenges of the ITER program.read more
Citations
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Journal ArticleDOI
Design and first applications of the ITER integrated modelling & analysis suite
Frederic Imbeaux,S. D. Pinches,J.B. Lister,Y. Buravand,T.A. Casper,B. P. Duval,B. Guillerminet,M. Hosokawa,Wayne A Houlberg,P. Huynh,S.H. Kim,Gabriele Manduchi,Michal Owsiak,Bartek Palak,Marcin Plociennik,Guy Rouault,Olivier Sauter,Pär Strand +17 more
TL;DR: The ITER Integrated Modelling & Analysis Suite (IMAS) will support both plasma operation and research activities on the ITER tokamak experiment and will be accessible to all ITER members as a key tool for the scientific exploitation of ITER.
Journal ArticleDOI
Nonlinear ELM simulations based on a nonideal peeling–ballooning model using the BOUT++ code
TL;DR: A minimum set of equations based on the peeling-ballooning model with nonideal physics effects (diamagnetic drift, E × B drift, resistivity and anomalous electron viscosity) is found to simulate pedestal collapse when using the BOUT++ simulation code, developed in part from the original fluid edge code BOUT as mentioned in this paper.
Journal ArticleDOI
METIS: a fast integrated tokamak modelling tool for scenario design
J.F. Artaud,Frederic Imbeaux,J. Garcia,G. Giruzzi,T. Aniel,V. Basiuk,A. Bécoulet,Clarisse Bourdelle,Y. Buravand,J. Decker,R. J. Dumont,L.-G. Eriksson,Xavier Garbet,R. Guirlet,G.T. Hoang,P. Huynh,E. Joffrin,X. Litaudon,Patrick Maget,D. Moreau,Rémy Nouailletas,B. Pégourié,Y. Peysson,M. Schneider,Jakub Urban +24 more
TL;DR: A first comprehensive description of the METIS suite is given: overall structure of the code, main available models, details on the simulation workflow and numerical implementation, and examples of applications to the analysis of experimental discharges and the predictions of ITER scenarios are given.
Journal ArticleDOI
Non-linear MHD modelling of ELM triggering by pellet injection in DIII-D and implications for ITER
Shimpei Futatani,Gta Guido Huijsmans,A. Loarte,Larry R. Baylor,Nicolas Jc Commaux,T.C. Jernigan,M.E. Fenstermacher,M.E. Fenstermacher,C.J. Lasnier,C.J. Lasnier,T.H. Osborne,B. Pégourié +11 more
TL;DR: In this article, the impact of the localized pressure perturbation caused by pellet injection in the DIII-D tokamak has been simulated with the non-linear MHD code JOREK with a view to validating its physics models.
Journal ArticleDOI
ELM control with RMP: Plasma response models and the role of edge peeling response
Yueqiang Liu,C. J. Ham,A. Kirk,Li Li,Li Li,Li Li,A. Loarte,D. A. Ryan,Youwen Sun,W. Suttrop,Xu Yang,Lina Zhou +11 more
TL;DR: In this article, the role of the edge peeling response to the RMP fields is illustrated as a key indicator for the ELM mitigation in low collisionality plasmas, in various tokamak devices.
References
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TL;DR: The Sustained Spheromak Physics Experiment (SSPX) as discussed by the authors was a high-temperature (Te up to 0.5 keV), coaxial helicity injection (CHI) formed by coaxial helical injection, with plasma duration of a few milliseconds following the high-current formation stage.
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Chapter 6: Steady state operation
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TL;DR: The actuators for heating and current drive that are necessary to produce and control the advanced tokamak discharges are discussed, including modelling and predictions for ITER, and specific control issues for steady state operation are discussed.
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Studies of plasma equilibrium and transport in a Tokamak fusion device with the inverse-variable technique
R. R. Khayrutdinov,V.E. Lukash +1 more
TL;DR: In this paper, an accurate and efficient model for studying the evolution of tokamak plasmas is described, where the equilibrium problem for a plasma with a free boundary is solved using the "inverse variable" technique.