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Dive into the research topics where G. J. Kramer is active.

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Featured researches published by G. J. Kramer.


Physics of Plasmas | 2011

Measurements and modeling of Alfvén eigenmode induced fast ion transport and loss in DIII-D and ASDEX Upgrade

M. A. Van Zeeland; W.W. Heidbrink; R. K. Fisher; M. Garcia Munoz; G. J. Kramer; D. C. Pace; R. B. White; S. Aekaeslompolo; M. E. Austin; J. E. Boom; I. G. J. Classen; S. da Graça; B. Geiger; M. Gorelenkova; N.N. Gorelenkov; A.W. Hyatt; N.C. Luhmann; M. Maraschek; G. R. McKee; R.A. Moyer; C.M. Muscatello; R. Nazikian; Hae-Sim Park; S. Sharapov; W. Suttrop; G. Tardini; Benjamin Tobias; Y. B. Zhu; Diii-D

Neutral beam injection into reversed magnetic shear DIII-D and ASDEX Upgrade plasmas produces a variety of Alfvenic activity including toroidicity-induced Alfven eigenmodes and reversed shear Alfven eigenmodes (RSAEs). These modes are studied during the discharge current ramp phase when incomplete current penetration results in a high central safety factor and increased drive due to multiple higher order resonances. Scans of injected 80 keV neutral beam power on DIII-D showed a transition from classical to AE dominated fast ion transport and, as previously found, discharges with strong AE activity exhibit a deficit in neutron emission relative to classical predictions. By keeping beam power constant and delaying injection during the current ramp, AE activity was reduced or eliminated and a significant improvement in fast ion confinement observed. Similarly, experiments in ASDEX Upgrade using early 60 keV neutral beam injection drove multiple unstable RSAEs. Periods of strong RSAE activity are accompanied ...


Physics of Plasmas | 2009

Experimental studies on fast-ion transport by Alfven wave avalanches on the National Spherical Torus Experiment

Mario Podesta; W.W. Heidbrink; D. Liu; E. Ruskov; R.E. Bell; D. S. Darrow; E.D. Fredrickson; N.N. Gorelenkov; G. J. Kramer; Benoit P. Leblanc; S. S. Medley; A.L. Roquemore; N.A. Crocker; S. Kubota; H. Yuh

Fast-ion transport induced by Alfven eigenmodes (AEs) is studied in beam-heated plasmas on the National Spherical Torus Experiment [Ono et al., Nucl. Fusion 40, 557 (2000)] through space, time, and energy resolved measurements of the fast-ion population. Fast-ion losses associated with multiple toroidicity-induced AEs (TAEs), which interact nonlinearly and terminate in avalanches, are characterized. A depletion of the energy range >20u2002keV, leading to sudden drops of up to 40% in the neutron rate over 1 ms, is observed over a broad spatial range. It is shown that avalanches lead to a relaxation of the fast-ion profile, which in turn reduces the drive for the instabilities. The measured radial eigenmode structure and frequency of TAEs are compared with the predictions from a linear magnetohydrodynamics stability code. The partial disagreement suggests that nonlinearities may compromise a direct comparison between experiment and linear theory.


Physics of Plasmas | 2009

Modeling fast-ion transport during toroidal Alfvén eigenmode avalanches in National Spherical Torus Experiment

E.D. Fredrickson; N.A. Crocker; R.E. Bell; D. S. Darrow; N.N. Gorelenkov; G. J. Kramer; S. Kubota; F. M. Levinton; D. Liu; S. S. Medley; M. Podestá; K. Tritz; R. B. White; H. Yuh

Experiments on the National Spherical Torus Experiment [M. Ono et al., Nucl. Fusion 40, 557 (2000)] found strong bursts of toroidal Alfven eigenmode (TAE) activity correlated with abrupt drops in the neutron rate. A fairly complete data set offers the opportunity to benchmark the NOVA [C. Z. Cheng, Phys. Rep. 211, 1 (1992)] and ORBIT [R. B. White and M. S. Chance, Phys. Fluids 27, 2455 (1984)] codes in the low aspect ratio tokamak (ST) geometry. The internal structure of TAE was modeled with NOVA and good agreement is found with measurements made with an array of five fixed-frequency reflectometers. The fast-ion transport resulting from these bursts of multiple TAE was then modeled with the ORBIT code. The simulations are reasonably consistent with the observed drop in neutron rate, however, further refinements in both the simulation of the TAE structure and in the modeling of the fast-ion transport are needed. Benchmarking stability codes against present experiments is an important step in developing the...


Plasma Physics and Controlled Fusion | 2014

Modulation of prompt fast-ion loss by applied n=2 fields in the DIII-D tokamak

M. A. Van Zeeland; N.M. Ferraro; W.W. Heidbrink; G. J. Kramer; D. C. Pace; X. Chen; T.E. Evans; R. K. Fisher; M. Garcia-Munoz; J.M. Hanson; M.J. Lanctot; L. L. Lao; R.A. Moyer; R. Nazikian; D. M. Orlov

Energy and pitch angle resolved measurements of escaping neutral beam ions (E ≈ 80 keV) have been made during DIII-D L-mode discharges with applied, slowly rotating, n = 2 magnetic perturbations. Data from separate scintillator detectors (FILDs) near and well below the plasma midplane show fast-ion losses correlated with the internal coil (I-coil) fields. The dominant fast-ion loss signals are observed to decay within one poloidal transit time after beam turn-off indicating they are primarily prompt loss orbits. Also, during application of the rotating I-coil fields, outboard midplane edge density and bremsstrahlung emission profiles exhibit a radial displacement of up to δR ≈ 1 cm. Beam deposition and full orbit modeling of these losses using M3D-C1 calculations of the perturbed kinetic profiles and fields reproduce many features of the measured losses. In particular, the predicted phase of the modulated loss signal with respect to the I-coil currents is in close agreement with FILD measurements as is the relative amplitudes of the modulated losses for the co and counter-current beam used in the experiment. These simulations show modifications to the beam ion birth profile and subsequent prompt loss due to changes in the edge density; however, the dominant factor causing modulation of the losses to the fast-ion loss detectors is the perturbed magnetic field (δB/B ≈ 10−3 in the plasma). Calculations indicate total prompt loss to the DIII-D wall can increase with application of the n = 2 perturbation by up to 7% for co-current injected beams and 3% for counter-current injected beams depending on phase of the perturbation relative to the injected beam.


Nuclear Fusion | 2012

Alfvén eigenmode stability and fast ion loss in DIII-D and ITER reversed magnetic shear plasmas

M. A. Van Zeeland; N.N. Gorelenkov; W. W. Heidbrink; G. J. Kramer; D. Spong; M. E. Austin; R. K. Fisher; M. Garcia Munoz; M. Gorelenkova; N. C. Luhmann Jr.; M. Murakami; R. Nazikian; D. C. Pace; J. M. Park; B. Tobias; R. B. White

Neutral beam injection into reversed-magnetic shear DIII-D plasmas produces a variety of Alfv?nic activity including toroidicity-induced Alfv?n eigenmodes (TAEs) and reversed shear Alfv?n eigenmodes (RSAEs). With measured equilibrium profiles as inputs, the ideal MHD code NOVA is used to calculate eigenmodes of these plasmas. The postprocessor code NOVA-K is then used to perturbatively calculate the actual stability of the modes, including finite orbit width and finite Larmor radius effects, and reasonable agreement with the spectrum of observed modes is found. Using experimentally measured mode amplitudes, fast ion orbit following simulations have been carried out in the presence of the NOVA calculated eigenmodes and are found to reproduce the dominant energy, pitch and temporal evolution of the losses measured using a large bandwidth scintillator diagnostic. The same analysis techniques applied to a DT 8 MA ITER steady-state plasma scenario with reversed-magnetic shear and both beam ion and alpha populations show Alfv?n eigenmode instability. Both RSAEs and TAEs are found to be unstable with maximum growth rates occurring for toroidal mode number n?=?6 and the majority of the drive coming from fast ions injected by the 1?MeV negative ion beams. AE instability due to beam ion drive is confirmed by the non-perturbative code TAEFL. Initial fast ion orbit following simulations using the unstable modes with a range of amplitudes (?B/B?=?10?5?10?3) have been carried out and show negligible fast ion loss. The lack of fast ion loss is a result of loss boundaries being limited to large radii and significantly removed from the actual modes themselves.


Nuclear Fusion | 2013

Fast-ion energy loss during TAE avalanches in the National Spherical Torus Experiment

E.D. Fredrickson; N.A. Crocker; D. S. Darrow; N.N. Gorelenkov; G. J. Kramer; S. Kubota; M. Podesta; R. B. White; A. Bortolon; S.P. Gerhardt; R.E. Bell; A. Diallo; Benoit P. Leblanc; F. M. Levinton; H. Yuh

Strong toroidal Alfven eigenmode (TAE) avalanches on NSTX, the National Spherical Torus Experiment (Ono et al 2000 Nucl. Fusion 40 557) are typically correlated with drops in the neutron rate in the range 5–15%. In previous studies of avalanches in L-mode plasmas, these neutron drops were found to be consistent with modelled losses of fast ions. Here we expand the study to TAE avalanches in NSTX H-mode plasmas with improved analysis techniques. At the measured TAE mode amplitudes, simulations with the ORBIT code predict that fast ion losses are negligible. However, the simulations predict that the TAE scatter the fast ions in energy, resulting in a small (≈5–6%) drop in fast ion β. The net decrease in energy of the fast ions is sufficient to account for about 50% of the drop in neutron rate, redistribution for ≈40%, and fast ion losses account for only ≈10%. This loss of energy from the fast ion population is comparable to the estimated energy lost by damping from the Alfven wave during the burst. The previously studied TAE avalanches in L-mode are re-evaluated using an improved calculation of the potential fluctuations in the ORBIT code near the separatrix.


Physics of Plasmas | 2007

Coupling of global toroidal Alfven eigenmodes and reversed shear Alfven eigenmodes in DIII-D

M. A. Van Zeeland; M. E. Austin; N. N. Gorelenkov; W.W. Heidbrink; G. J. Kramer; M. A. Makowski; G.R. McKee; R. Nazikian; E. Ruskov; Alan D. Turnbull

Reversed shear Alfven eigenmodes (RSAEs) are typically thought of as being localized near the minima in the magnetic safety factor profile, however, their spatial coupling to global toroidal Alfven eigenmodes (TAEs) has been observed in DIII-D discharges. For a decreasing minimum magnetic safety factor, the RSAE frequency chirps up through that of stable and unstable TAEs. Coupling creates a small gap at the frequency degeneracy point forming two distinct global modes. The core-localized RSAE mode structure changes and becomes temporarily global. Similarly, near the mode frequency crossing point, the global TAE extends deeper into the plasma core. The frequency splitting and spatial structure of the two modes throughout the various coupling stages, as measured by an array of internal fluctuation diagnostics, are in close agreement with linear ideal MHD calculations using the NOVA code. The implications of this coupling for eigenmode stability is also investigated and marked changes are noted throughout th...


Nuclear Fusion | 2013

Fast-wave power flow along SOL field lines in NSTX and the associated power deposition profile across the SOL in front of the antenna

R.J. Perkins; J.-W. Ahn; R.E. Bell; A. Diallo; S.P. Gerhardt; T.K. Gray; D.L. Green; E. F. Jaeger; J. C. Hosea; M.A. Jaworski; Benoit P. Leblanc; G. J. Kramer; A.G. McLean; R. Maingi; C. K. Phillips; M. Podesta; L. Roquemore; P. M. Ryan; S.A. Sabbagh; F. Scotti; G. Taylor; J. R. Wilson

Fast-wave heating and current drive efficiencies can be reduced by a number of processes in the vicinity of the antenna and in the scrape off layer (SOL). On NSTX from around 25% to more than 60% of the high-harmonic fast-wave power can be lost to the SOL regions, and a large part of this lost power flows along SOL magnetic field lines and is deposited in bright spirals on the divertor floor and ceiling. We show that field-line mapping matches the location of heat deposition on the lower divertor, albeit with a portion of the heat outside of the predictions. The field-line mapping can then be used to partially reconstruct the profile of lost fast-wave power at the midplane in front of the antenna, and the losses peak close to the last closed flux surface (LCFS) as well as the antenna. This profile suggests a radial standing-wave pattern formed by fast-wave propagation in the SOL, and this hypothesis will be tested on NSTX-U. Advanced RF codes must reproduce these results so that such codes can be used to understand this edge loss and to minimize RF heat deposition and erosion in the divertor region on ITER.


Physics of Plasmas | 2008

Alfvén cascade modes at high β in the National Spherical Torus Experiment

N.A. Crocker; E. D. Fredrickson; N. N. Gorelenkov; G. J. Kramer; D. S. Darrow; W.W. Heidbrink; S. Kubota; F. M. Levinton; H. Yuh; J. Menard; B. LeBlanc; R. E. Bell

Alfven cascade (AC) modes are observed in the National Spherical Torus Experiment [M. Ono et al., Nucl. Fusion 40, 557 (2000)] reversed shear plasmas over a wide range (up to ∼25% on axis, or ∼11% at minimum q) of β (ratio of kinetic pressure to magnetic pressure). At low β, the AC mode spectrum shows characteristics similar to conventional tokamaks. At higher β, distinct β and ∇β effects are observed in the spectrum, including a significant reduction in the relative size of the frequency sweep and a toroidal mode number dependence in the minimum mode frequency. AC mode structure is obtained using reflectometry. Fast-ion loss associated with AC mode activity is observed. AC mode polarization at the plasma edge is consistent with expectation. Magnetohydrodynamic (MHD) spectroscopy is shown to be usable to determine qmin at both low β and high β. Observed AC mode structure and frequency are found to be consistent with calculations for the same plasma conditions and geometry using the linear, ideal MHD hybri...


Nuclear Fusion | 2013

Simulation of localized fast-ion heat loads in test blanket module simulation experiments on DIII-D

G. J. Kramer; A.G. McLean; N.H. Brooks; R.V. Budny; X. Chen; W.W. Heidbrink; Taina Kurki-Suonio; R. Nazikian; T. Koskela; M.J. Schaffer; K. Shinohara; J.A. Snipes; M. A. Van Zeeland

Infrared imaging of hot spots induced by localized magnetic perturbations using the test blanket module (TBM) mock-up on DIII-D is in good agreement with beam-ion loss simulations. The hot spots were seen on the carbon protective tiles surrounding the TBM as they reached temperatures over 1000 °C. The localization of the hot spots on the protective tiles is in fair agreement with fast-ion loss simulations using a range of codes: ASCOT, SPIRAL and OFMCs while the codes predicted peak heat loads that are within 30% of the measured ones. The orbit calculations take into account the birth profile of the beam ions as well as the scattering and slowing down of the ions as they interact with the localized TBM field. The close agreement between orbit calculations and measurements validate the analysis of beam-ion loss calculations for ITER where ferritic material inside the tritium breeding TBMs is expected to produce localized hot spots on the first wall.

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W.W. Heidbrink

University of California

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R. Nazikian

Princeton Plasma Physics Laboratory

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M. Podesta

Princeton Plasma Physics Laboratory

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N.N. Gorelenkov

Princeton Plasma Physics Laboratory

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M. E. Austin

University of Texas at Austin

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