Novel aspects of plasma control in ITER
- General Atomics P.O. Box 85608, San Diego, California 92186-5608 (United States)
- CREATE/University of Naples Federico II, Napoli (Italy)
- ITER Organization, St. Paul Lez durance Cedex (France)
- Eindhoven University of Technology, Eindhoven (Netherlands)
- Max-Planck Institut für Plasmaphysik, Garching (Germany)
- Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543-0451 (United States)
- Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Federale de Lausanne, Lausanne (Switzerland)
- CEA, IRFM, 13108 St. Paul-lez Durance (France)
- Lehigh University, Bethlehem, Pennsylvania (United States)
ITER plasma control design solutions and performance requirements are strongly driven by its nuclear mission, aggressive commissioning constraints, and limited number of operational discharges. In addition, high plasma energy content, heat fluxes, neutron fluxes, and very long pulse operation place novel demands on control performance in many areas ranging from plasma boundary and divertor regulation to plasma kinetics and stability control. Both commissioning and experimental operations schedules provide limited time for tuning of control algorithms relative to operating devices. Although many aspects of the control solutions required by ITER have been well-demonstrated in present devices and even designed satisfactorily for ITER application, many elements unique to ITER including various crucial integration issues are presently under development. We describe selected novel aspects of plasma control in ITER, identifying unique parts of the control problem and highlighting some key areas of research remaining. Novel control areas described include control physics understanding (e.g., current profile regulation, tearing mode (TM) suppression), control mathematics (e.g., algorithmic and simulation approaches to high confidence robust performance), and integration solutions (e.g., methods for management of highly subscribed control resources). We identify unique aspects of the ITER TM suppression scheme, which will pulse gyrotrons to drive current within a magnetic island, and turn the drive off following suppression in order to minimize use of auxiliary power and maximize fusion gain. The potential role of active current profile control and approaches to design in ITER are discussed. Issues and approaches to fault handling algorithms are described, along with novel aspects of actuator sharing in ITER.
- OSTI ID:
- 22408051
- Journal Information:
- Physics of Plasmas, Vol. 22, Issue 2; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA); ISSN 1070-664X
- Country of Publication:
- United States
- Language:
- English
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