Published November 1, 2019 | Version v1
Journal article

Progress in disruption prevention for ITER

  • 1. General Atomics, PO Box 85608, San Diego, CA 92186-5608 (United States)
  • 2. Consorzio RFX, corso Stati Uniti 4, 35127 Padova (Italy)
  • 3. Columbia University, New York, NY 10027 (United States)
  • 4. ITER Organization, Route de Vinon sur Verdon, 13067 St Paul Lez Durance (France)
  • 5. Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA (United States)
  • 6. Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)
  • 7. National Fusion Research Institute, Daejon (Korea, Republic of)
  • 8. Princeton Plasma Physics Laboratory, Princeton, NJ 08543 (United States)
  • 9. École Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne (Switzerland)
  • 10. CCFE Fusion Association, Culham Science Centre, Abingdon, United Kingdom of Great Britain and Northern Ireland (United Kingdom)
  • 11. Max-Planck-Institute für Plasma Physik, D-85748, Garching (Germany)

Description

Key plasma physics and real-time control elements needed for robustly stable operation of high fusion power discharges in ITER have been demonstrated in recent research worldwide. Recent analysis has identified the current density profile as the main drive for disruptive instabilities in discharges simulating ITER's baseline scenario with high and low external torque. Ongoing development of model-based profile control and active control of magnetohydrodynamic instabilities is improving the stability of multiple scenarios. Significant advances have been made toward real-time physics-based prediction of instabilities, including path-oriented analysis, active sensing, and machine learning techniques for prediction that are beginning to go beyond simple disruption mitigation trigger applications. Active intervention contributes to prevention of disruptions, including forced rotation of magnetic islands to prevent wall locking, and localized heating/current drive to shrink the islands. Stable discharge rampdowns have been achieved with the fastest ITER-like scaled current ramp rates, while maintaining an X-point configuration. These elements are being integrated into stable operating scenarios and new event-handling systems for off-normal events in order to develop the physics basis and techniques for robust control in ITER. (paper)

Availability note (English)

Available from http://dx.doi.org/10.1088/1741-4326/ab15de

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
59
Journal Issue
11
Journal Page Range
[12 p.]
ISSN
0029-5515
CODEN
NUFUAU

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51093985
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
BASES; CONTROL ELEMENTS; CURRENT DENSITY; INSTABILITY; ITER TOKAMAK; MAGNETIC ISLANDS; ROTATING PLASMA
Descriptors DEC
CLOSED PLASMA DEVICES; MAGNETIC FIELD CONFIGURATIONS; PLASMA; REACTOR COMPONENTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS