Results 1 to 10 of about 15,788,591 (215)
Current State of DIII-D Plasma Control System
Fusion Engineering and Design, 2020 The DIII-D Plasma Control System (PCS) is a comprehensive software and hardware system used in real-time data acquisition and feedback control of numerous actuators on the DIII-D tokamak. It regulates many plasma characteristics including shape, position,
Cristina Rea, Joseph Rauch, J Ferron
exaly +2 more sources
Results from core-edge experiments in high Power, high performance plasmas on DIII-D
Nuclear Materials and Energy, 2017 Significant challenges to reducing divertor heat flux in highly powered near-double null divertor (DND) hybrid plasmas, while still maintaining both high performance metrics and low enough density for application of RF heating, are identified.
Tom Petrie, D C Pace, T C Luce
exaly +3 more sources
Advances in radiated power control at DIII-D
Nuclear Materials and Energy, 2019 Feedback control of radiated power from the lower divertor Prad, div, L has been implemented in the DIII-D Plasma Control System (PCS). A realtime sensor for Prad, div, L has been constructed from 12 foil bolometer channels which agrees with standard ...
D. Eldon +9 more
doaj +2 more sources
Accelerating discoveries at DIII-D with the Integrated Research Infrastructure
Frontiers in PhysicsDIII-D research is being accelerated by leveraging high performance computing (HPC) and data resources available through the National Energy Research Scientific Computing Center (NERSC) Superfacility initiative.
Osborne T, Smith S P, Nazikian R
exaly +3 more sources
Runaway electron deconfinement in SPARC and DIII-D by a passive 3D coil [PDF]
Nuclear Fusion, 2022 The operation of a 3D coil—passively driven by the current quench (CQ) loop voltage—for the deconfinement of runaway electrons (REs) is modeled for disruption scenarios in the SPARC and DIII-D tokamaks.
V. Izzo +9 more
semanticscholar +1 more source
Vertical control of DIII-D discharges with strong negative triangularity
Plasma Physics and Controlled Fusion, 2023 Through predictive modeling validated by a series of experiments on DIII-D, the vertical stability of low β diverted plasmas with strong negative triangularity (NT) ( δ∼−0.6 ) is assessed. As a result of their unique magnetic geometry, NT plasmas feature
A. Nelson +7 more
semanticscholar +1 more source
Nuclear Fusion, 2021 Diverted discharges at negative triangularity on the DIII-D tokamak sustain normalized confinement and pressure levels typical of standard H-mode scenarios (H 98y2 ≃ 1, β N ≃ 3) without developing an edge pressure pedestal, despite the auxiliary power ...
A. Marinoni +20 more
semanticscholar +1 more source
Divertor erosion in DIII-D [PDF]
Journal of Nuclear Materials, 1999 Abstract Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. For attached divertors (Te > 40 eV), outer strike point (OSP) erosion rates exceed 10 cm/exposure-year, physical sputtering is dominant and the effective sputtering yield, Y, is greater than 10%.
Whyte, D. G. +7 more
openaire +3 more sources
Data-driven profile prediction for DIII-D
, 2021 A new, fully data-driven algorithm has been developed that uses a neural network to predict plasma profiles on a scale of τ E into the future given an actuator trajectory and the plasma state history.
J. Abbate, R. Conlin, E. Kolemen
semanticscholar +1 more source
The high-power helicon program at DIII-D: gearing up for first experiments
Nuclear Fusion, 2021 Helicon current drive (CD), also called fast wave CD in the lower hybrid range of frequencies, has long been regarded as a promising CD tool for reactor grade plasmas.
Van Compernolle +31 more
semanticscholar +1 more source