Demonstration of ITER operational scenarios on DIII-D
Creators
- 1. Department of Physics and Astronomy, and PSTI, University of California, Los Angeles, CA 90095 (United States)
- 2. General Atomics, PO Box 85608, San Diego, CA 92186-5608 (United States)
- 3. Oak Ridge National Laboratory, Oak Ridge, TN (United States)
- 4. Department of Applied Physics and Applied Mathematics, Columbia University, New York, NY (United States)
- 5. Princeton Plasma Physics Laboratory, Princeton, NJ (United States)
- 6. Lawrence Livermore National Laboratory, Livermore, CA (United States)
- 7. Euratom/CCFE Fusion Association, Culham Science Centre, Oxon OX14 3DB (United Kingdom)
- 8. Department of Energy Physics, University of Wisconsin-Madison, Madison, WI (United States)
Description
The DIII-D programme has recently initiated an effort to provide suitably scaled experimental evaluations of four primary ITER operational scenarios. New and unique features of this work are that the plasmas incorporate essential features of the ITER scenarios and anticipated operating characteristics; e.g. the plasma cross-section, aspect ratio and value of I/aB of the DIII-D discharges match the ITER design, with size reduced by a factor of 3.7. Key aspects of all four scenarios, such as target values for βN and H98, have been replicated successfully on DIII-D, providing an improved and unified physics basis for transport and stability modelling, as well as for performance extrapolation to ITER. In all four scenarios, normalized performance equals or closely approaches that required to realize the physics and technology goals of ITER, and projections of the DIII-D discharges are consistent with ITER achieving its goals of ≥400 MW of fusion power production and Q ≥ 10. These studies also address many of the key physics issues related to the ITER design, including the L-H transition power threshold, the size of edge localized modes, pedestal parameter scaling, the impact of tearing modes on confinement and disruptivity, beta limits and the required capabilities of the plasma control system. An example of direct influence on the ITER design from this work is a modification of the physics requirements for the poloidal field coil set at 15 MA, based on observations that the inductance in the baseline scenario case evolves to a value that lies outside the original ITER specification.
Availability note (English)
Available from http://dx.doi.org/10.1088/0029-5515/50/7/075005Additional details
Identifiers
- DOI
- 10.1088/0029-5515/50/7/075005;
- PII
- S0029-5515(10)43407-9;
Publishing Information
- Journal Title
- Nuclear Fusion
- Journal Volume
- 50
- Journal Issue
- 7
- Journal Page Range
- [8 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
- 42024227
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ASPECT RATIO; CONTROL SYSTEMS; DESIGN; DOUBLET-3 DEVICE; EDGE LOCALIZED MODES; ITER TOKAMAK; PLASMA; TEARING INSTABILITY
- Descriptors DEC
- CLOSED PLASMA DEVICES; DIMENSIONLESS NUMBERS; INSTABILITY; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS