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Nuclear Fusion, ISSN 0029-5515, 02/2012, Volume 52, Issue 2, pp. 1 - 17
This paper presents the results from a systematic study of low-to-high confinement transition (L-H transition) in Alcator C-Mod lower single null plasmas, with... 
TRANSITION | PHYSICS, FLUIDS & PLASMAS | REGIME | JET | PHYSICS, NUCLEAR | TURBULENCE | ASDEX | Confinement | Nuclear fusion | Amplitudes | Drift | Tokamak devices | Plasmas | Density | Discharge
Journal Article
Nature Physics, ISSN 1745-2473, 10/2017, Volume 13, Issue 10, pp. 973 - 978
Journal Article
Plasma Physics and Controlled Fusion, ISSN 0741-3335, 05/2016, Volume 58, Issue 7, pp. 74005 - 74015
As in many of today's tokamaks, plasma start-up in ITER will be performed in limiter configuration on either the inner or outer midplane first wall (FW). The... 
tokamak | SOL width | scaling | ITER | SOL decay length | TRANSPORT | PHYSICS, FLUIDS & PLASMAS | SCRAPE-OFF-LAYER | Panels | Databases | Decay | Tokamak devices | Plasmas | Heat flux | Walls | Heat transfer
Journal Article
Nuclear Materials and Energy, ISSN 2352-1791, 08/2017, Volume 12, pp. 91 - 99
New techniques that attempt to more fully exploit spectroscopic diagnostics in the divertor and pedestal region during highly dissipative scenarios are... 
ASDEX UPGRADE | PROFILES | NUCLEAR SCIENCE & TECHNOLOGY | PLASMA EDGE | EDGE PHYSICS | INCIDENCE SPECTROMETER
Journal Article
Nuclear Fusion, ISSN 0029-5515, 06/2007, Volume 47, Issue 6, pp. S203 - S263
Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999 Nucl. Fusion 39 2137-2664), in understanding the processes that will... 
HYDROGEN ISOTOPE RETENTION | PLASMA-FACING COMPONENTS | PHYSICS, FLUIDS & PLASMAS | SHAPED PUMPED DIVERTOR | ASDEX UPGRADE DIVERTOR | ELMY H-MODE | HT-7 SUPERCONDUCTING TOKAMAK | EDGE LOCALIZED MODES | DIII-D TOKAMAK | PHYSICS, NUCLEAR | ALCATOR-C-MOD | SCRAPE-OFF-LAYER
Journal Article
Nuclear Fusion, ISSN 0029-5515, 09/2013, Volume 53, Issue 9, pp. 93031 - 7
Amulti-machine database for the H-mode scrape-off layer power fall-off length, lambda(q) in JET, DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled... 
HEAT-FLUX | TRANSPORT | ALCATOR C-MOD | PHYSICS, FLUIDS & PLASMAS | FLUCTUATIONS | JET | PHYSICS, NUCLEAR | ASDEX | Databases | Regression | Nuclear power generation | Mathematical models | Tokamak devices | Combustion | Inclusions | Carbon
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 07/2013, Volume 438, pp. S84 - S89
Growth of tungsten nano-tendrils (“fuzz”) has been observed for the first time in the divertor region of a high-power density tokamak experiment. After 14... 
NUCLEAR SCIENCE & TECHNOLOGY | MATERIALS SCIENCE, MULTIDISCIPLINARY | MINING & MINERAL PROCESSING | Comparative analysis | Plasma physics | Tungsten | Voids | Langmuir-Blodgett films | Tokamak devices | Nanostructure | Helium | Density | Strikes
Journal Article
Review of Scientific Instruments, ISSN 0034-6748, 03/2012, Volume 83, Issue 3, pp. 033501 - 033501-7
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 2003, Volume 313, pp. 995 - 999
Parallel and E × B plasma flows near the separatrix on the outside midplane of Alcator C-Mod are investigated with a scanning probe for a range plasma... 
Toroidal rotation | [formula omitted] flow | Plasma flow | Mach probe | Fluctuation phase velocity | E × B flow | toroidal rotation | fluctuation phase velocity | MATERIALS SCIENCE, MULTIDISCIPLINARY | E x B flow | ASYMMETRIES | SOL | plasma flow | DIVERTOR | NUCLEAR SCIENCE & TECHNOLOGY | MINING & MINERAL PROCESSING | PARTICLE-TRANSPORT | TOKAMAK
Journal Article
Review of Scientific Instruments, ISSN 0034-6748, 02/2016, Volume 87, Issue 2, p. 023504
Mitigation of the intense heat flux to the divertor is one of the outstanding problems in fusion energy. One technique that has shown promise is impurity... 
PLANT | ASDEX UPGRADE | INSTRUMENTS & INSTRUMENTATION | PHYSICS, APPLIED | ITER | Temperature | Time signals | Thermocouples | Analog computers | Surface temperature | Control systems | Tokamak devices | Time measurement | Real time | Plasma control | Heat flux | Pulse duration | Heat | Impurities | Feedback | Energy dissipation | Proportional integral derivative | Heat transfer
Journal Article
NUCLEAR FUSION, ISSN 0029-5515, 08/2019, Volume 59, Issue 8, p. 86017
The 'Super H-Mode' regime is predicted to enable pedestal height and fusion performance substantially higher than standard H-Mode operation. This regime exists... 
pedestal | Super H Mode | Alcator C-Mod | PHYSICS, FLUIDS & PLASMAS | tokamak | EPED | DIII-D | fusion gain | 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Journal Article
Nuclear Fusion, ISSN 0029-5515, 12/2013, Volume 53, Issue 12, pp. 122001 - 5
A theory-based scaling for the characteristic length of a circular, limited tokamak scrape-off layer (SOL) is obtained by considering the balance between... 
TRANSITION | PHYSICS, NUCLEAR | TRANSPORT | TURBULENCE | PHYSICS, FLUIDS & PLASMAS | Turbulence | Turbulent flow | Fluid dynamics | Circularity | Fluid flow | Nonlinearity | Tokamak devices | Plasmas
Journal Article
Nuclear Fusion, ISSN 0029-5515, 09/2013, Volume 53, Issue 9, pp. 93024 - 19
Joint experiment/theory/modelling research has led to increased confidence in predictions of the pedestal height in ITER. This work was performed as part of a... 
DENSITY | PROFILES | INSTABILITY | TEMPERATURE | EQUILIBRIA | PHYSICS, FLUIDS & PLASMAS | CONFINEMENT | ARBITRARY COLLISIONALITY | DIII-D | TRANSPORT MODELS | BOOTSTRAP-CURRENT | Extrapolation | Turbulence | Stability | Confidence | Mathematical models | Models | Modelling | Transport
Journal Article