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Fonck, R.; Barr, J.; Bodner, G.; Bongard, M.; Burke, M.; Kriete, D.; Perry, J.; Reusch, J.; Schlossberg, D.; Sovinec, C.; Thome, K., E-mail: rjfonck@wisc.edu
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material2018
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material2018
AbstractAbstract
[en] Full text: Studies at near-unity aspect ratio offer unique insights into the high confinement (H-mode) regime and support development of novel startup scenarios. Ohmic H-mode operation has been attained at A < 1.3. Edge plasma parameters permit probe measurements of the edge pedestal, including the local current density profile, with high spatial and temporal resolution. H-mode plasmas have standard L-H transition phenomena: a drop in Dα radiation; the formation of pressure and current pedestals; field-aligned filament ejection during ELMs; and a doubling of energy confinement time from H98∼0.5 to ∼1. The L-H power threshold PLH increases monotonically with ne, consistent with the ITPA08 empirical scaling used for ITER and the theoretical FM3 model. Unlike at high A, PLH is comparable in limited and single-null diverted topologies at A~1.2, consistent with FM3 predictions. The magnitude of PLH exceeds ITPA scalings by an order of magnitude, with PLH/PITPA08 increasing as A approaches 1. Multiple n modes are observed during two classes of ELMs, consistent with excitation of multiple peeling-ballooning modes. Small, type-III-like ELMs occur at POHPLH with n ¤ 4. Large, type-I-like ELMs occur with POH > PLH and intermediate 5 < n < 15. Helical edge current injection appears to suppress type-III ELM activity. Jedge(R, t) measurements across single ELMs show the nonlinear generation and expulsion of current-carrying filaments during the ELM crash. Local Helicity Injection (LHI) offers a nonsolenoidal tokamak startup technique. Helicity is injected via current sources at the plasma edge. A circuit model that treats the plasma as a resistive element with time-varying inductance reasonably predicts Ip(t). The electron confinement governs the power balance. Initial measurements show peaked Te and pressure profiles, which are comparable to Ohmic-like transport or moderately stochastic confinement. Extrapolation suggests Ip~1 MA may be achievable in NSTX-U. Resistive MHD simulations suggest Ip is built from current rings injected during reconnection between unstable helical current streams. Several experimental observations support this model: imaging of the merging current streams; n = 1 MHD activity and discrete current stream localized in the plasma edge; and anomalously high impurity ion heating in the edge region. (author)
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International Atomic Energy Agency, Division of Physical and Chemical Sciences, Vienna (Austria); 935 p; 3 May 2018; p. 151; FEC 2016: 26. IAEA Fusion Energy Conference; Kyoto (Japan); 17-22 Oct 2016; IAEA-CN--234-0690; Available as preprint from https://nucleus.iaea.org/sites/fusionportal/Shared%20Documents/FEC%202016/fec2016-preprints/preprint0690.pdf; PowerPoint presentation available from https://nucleus.iaea.org/sites/fusionportal/Shared%20Documents/FEC%202016/fec2016-material/material0690.pdf; Abstract only
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CHARGED PARTICLES, CLOSED PLASMA DEVICES, CONFINEMENT, DIMENSIONLESS NUMBERS, ELEMENTARY PARTICLES, FERMIONS, FLUID MECHANICS, HYDRODYNAMICS, IMPURITIES, INSTABILITY, LEPTONS, MAGNETIC CONFINEMENT, MECHANICS, PARTICLE PROPERTIES, PLASMA CONFINEMENT, PLASMA INSTABILITY, PLASMA MACROINSTABILITIES, SIMULATION, SPHEROMAK DEVICES, THERMONUCLEAR DEVICES, TOKAMAK DEVICES
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