Multi-device studies of pedestal physics and confinement in the I-mode regime
Journal Article
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· Nuclear Fusion
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- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); General Atomics
- General Atomics, San Diego, CA (United States)
- Max-Planck-Institut fur Plasmaphysik, Garching (Germany)
- Univ. of Texas, Austin, TX (United States)
- Max-Planck-Institut fur Plasmaphysik, Garching (Germany); EUROfusion - Programme Management Unit, Garching (Germany)
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Univ. of California San Diego, La Jolla, CA (United States); Univ. of York, York (United Kingdom)
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
- ITER Organization, St. Paul Lez Durance Cedex (France)
- Univ. of Wisconsin, Madison, WI (United States)
- Univ. of California, Los Angeles, CA (United States)
- Ecole Polytechnique Federale de Lausanne (EPFL), Lausanne (Switzerland)
This paper describes joint ITPA studies of the I-mode regime, which features an edge thermal barrier together with L-mode-like particle and impurity transport and no Edge Localized Modes (ELMs). The regime has been demonstrated on the Alcator C-Mod, ASDEX Upgrade and DIII-D tokamaks, over a wide range of device parameters and pedestal conditions. Dimensionless parameters at the pedestal show overlap across devices and extend to low collisionality. When they are matched, pedestal temperature profiles are also similar. Pedestals are stable to peeling ballooning modes, consistent with lack of ELMs. Access to Imode is independent of heating method (neutral beam injection, Ion Cyclotron and/or Electron Cyclotron Resonance Heating). Normalized energy confinement H98,y2 ≥ 1 has been achieved for a range of 3 ≤ q95 ≤ 4.9 and scales favourably with power. Changes in turbulence in the pedestal region accompany the transition from L-mode to I-mode. The L-I threshold increases with plasma density and current, and with device size, but has a weak dependence on toroidal magnetic field BT. The upper limit of power for I-modes, which is set by I-H transitions, increases with BT and the power range is largest on Alcator C-Mod at B > 5 T. Finally, issues for extrapolation to ITER and other future fusion devices are discussed.
- Research Organization:
- General Atomics, San Diego, CA (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
- Contributing Organization:
- Alcator C-Mod, ASDEX Upgrade and DIII-D Teams
- Grant/Contract Number:
- AC02-09CH11466; AC52-07NA27344; FC02-04ER54698; FG02-08ER54984; FG02-08ER54999; FG02-89ER53296; FG02-94ER54235; SC0012469
- OSTI ID:
- 1373884
- Alternate ID(s):
- OSTI ID: 1871410
OSTI ID: 1375941
OSTI ID: 1260287
- Report Number(s):
- LLNL-JRNL-834529
- Journal Information:
- Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 8 Vol. 56; ISSN 0029-5515
- Publisher:
- IOP ScienceCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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