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Dive into the research topics where I. Joseph is active.

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Featured researches published by I. Joseph.


Nuclear Fusion | 2008

RMP ELM suppression in DIII-D plasmas with ITER similar shapes and collisionalities

T.E. Evans; M. E. Fenstermacher; R.A. Moyer; T. H. Osborne; J. G. Watkins; P. Gohil; I. Joseph; M. J. Schaffer; Larry R Baylor; M. Becoulet; J.A. Boedo; Keith H. Burrell; J. S. deGrassie; K. H. Finken; Thomas C Jernigan; M. Jakubowski; C. J. Lasnier; M. Lehnen; Anthony William Leonard; J. Lonnroth; E. Nardon; V. Parail; O. Schmitz; B. Unterberg; W.P. West

Large Type-I edge localized modes (ELMs) are completely eliminated with small n = 3 resonant magnetic perturbations (RMP) in low average triangularity, , plasmas and in ITER similar shaped (ISS) plasmas, , with ITER relevant collisionalities . Significant differences in the RMP requirements and in the properties of the ELM suppressed plasmas are found when comparing the two triangularities. In ISS plasmas, the current required to suppress ELMs is approximately 25% higher than in low average triangularity plasmas. It is also found that the width of the resonant q95 window required for ELM suppression is smaller in ISS plasmas than in low average triangularity plasmas. An analysis of the positions and widths of resonant magnetic islands across the pedestal region, in the absence of resonant field screening or a self-consistent plasma response, indicates that differences in the shape of the q profile may explain the need for higher RMP coil currents during ELM suppression in ISS plasmas. Changes in the pedestal profiles are compared for each plasma shape as well as with changes in the injected neutral beam power and the RMP amplitude. Implications of these results are discussed in terms of requirements for optimal ELM control coil designs and for establishing the physics basis needed in order to scale this approach to future burning plasma devices such as ITER.


Nuclear Fusion | 2009

Overview of the results on divertor heat loads in RMP controlled H-mode plasmas on DIII-D

M. Jakubowski; T.E. Evans; M. E. Fenstermacher; M. Groth; C. J. Lasnier; A. W. Leonard; O. Schmitz; J. G. Watkins; T. Eich; W. Fundamenski; R.A. Moyer; R. C. Wolf; L.B. Baylor; J.A. Boedo; Keith H. Burrell; H. Frerichs; J. S. deGrassie; P. Gohil; I. Joseph; S. Mordijck; M. Lehnen; C.C. Petty; R.I. Pinsker; D. Reiter; T.L. Rhodes; U. Samm; M. J. Schaffer; P.B. Snyder; H. Stoschus; T.H. Osborne

In this paper the manipulation of power deposition on divertor targets at DIII-D by the application of resonant magnetic perturbations (RMPs) for suppression of large type-I edge localized modes (ELMs) is analysed. We discuss the modification of the ELM characteristics by the RMP applied. It is shown that the width of the deposition pattern in ELMy H-mode depends linearly on the ELM deposited energy, whereas in the RMP phase of the discharge those patterns are controlled by the externally induced magnetic perturbation. It was also found that the manipulation of heat transport due to the application of small, edge RMP depends on the plasma pedestal electron collisionality . We compare in this analysis RMP and no RMP phases with and without complete ELM suppression. At high 0.5 SRC=http://ej.iop.org/images/0029-5515/49/9/095013/nf307994in002.gif/>, the heat flux during the ELM suppressed phase is of the same order as the inter-ELM and the no-RMP phase. However, below this collisionality value, a slight increase in the total power flux to the divertor is observed during the RMP phase. This is most likely caused by a more negative potential at the divertor surface due to hot electrons reaching the divertor surface from the pedestal area along perturbed, open field lines.


Plasma Physics and Controlled Fusion | 2008

Aspects of three dimensional transport for ELM control experiments in ITER-similar shape plasmas at low collisionality in DIII-D

O. Schmitz; T.E. Evans; M. E. Fenstermacher; H. Frerichs; M. Jakubowski; M. J. Schaffer; A. Wingen; W.P. West; N. H. Brooks; Keith H. Burrell; J. S. deGrassie; Y. Feng; K.H. Finken; P. Gohil; M. Groth; I. Joseph; C. J. Lasnier; M. Lehnen; A. W. Leonard; S. Mordijck; R.A. Moyer; A. Nicolai; T.H. Osborne; D. Reiter; U. Samm; K. H. Spatschek; H. Stoschus; B. Unterberg; E. A. Unterberg; J. G. Watkins

A study of three-dimensional (3D) perturbed magnetic field structures and transport for edge localized mode control experiments with resonant magnetic perturbations at DIII-D is presented. We focus on ITER-Similar Shape plasmas at ITER relevant electron pedestal collisionalities . This study is performed in comparison with results from TEXTOR-Dynamic Ergodic Divertor circular limiter plasmas. For both experiments the magnetic field structure is analyzed in the vacuum paradigm—superimposing the external RMP field on the unperturbed equilibrium. For TEXTOR L-mode plasmas this description holds for normalized poloidal flux ΨN > 0.7 without tearing modes driven by the RMP field. For DIII-D H-mode plasmas the validity of this approach still needs to be established. In this paper a method is discussed to diagnose the degree of edge stochastization based on a comparison between modeled magnetic footprints on the divertor targets and experimental data. Clear evidence is presented for the existence of a generic separatrix perturbation causing striation of target particle fluxes. However, heat fluxes into these striations are small. This observation can be explained by accounting for the different heat and particle source locations and the 3D trajectories of the open, perturbed field lines toward the divertor target. Analysis of the transport characteristics filling the perturbed separatrix lobes based on initial EMC3/EIRENE modeling suggests the existence of open field lines connecting the stochastic edge to the target pattern. However, the width and inward most extent of the actual stochastic layer cannot yet be quantified.


Physics of Plasmas | 2008

Effect of island overlap on edge localized mode suppression by resonant magnetic perturbations in DIII-D

M.E. Fenstermacher; T.E. Evans; T.H. Osborne; M.J. Schaffer; M. P. Aldan; J.S. deGrassie; P. Gohil; I. Joseph; R.A. Moyer; P. B. Snyder; R. J. Groebner; M. Jakubowski; A.W. Leonard; O. Schmitz

Recent DIII-D [J. L. Luxon et al., Nucl. Fusion 43, 1813 (2003)] experiments show a correlation between the extent of overlap of magnetic islands induced in the edge plasma by perturbation coils and complete suppression of Type-I edge localized modes (ELMs) in plasmas with ITER-like electron pedestal collisionality νe*∼0.1, flux surface shape and low edge safety factor (q95≈3.6). With fixed amplitude n=3 resonant magnetic perturbation (RMP), ELM suppression is obtained only in a finite window in the edge safety factor (q95) consistent with maximizing the resonant component of the applied helical field. ELM suppression is obtained over an increasing range of q95 by either increasing the n=3 RMP strength, or by adding n=1 perturbations to “fill in” gaps between islands across the edge plasma. The suppression of Type-I ELMs correlates with a minimum width of the edge region having magnetic islands with Chirikov parameter >1.0, based on vacuum calculations of RMP mode components excluding the plasma response ...


Physics of Plasmas | 2006

The physics of edge resonant magnetic perturbations in hot tokamak plasmasa)

T.E. Evans; K.H. Burrell; M.E. Fenstermacher; R.A. Moyer; T.H. Osborne; M.J. Schaffer; W.P. West; L. W. Yan; J. Boedo; E. J. Doyle; G.L. Jackson; I. Joseph; C.J. Lasnier; A.W. Leonard; T.L. Rhodes; P. R. Thomas; J. G. Watkins; L. Zeng

Small edge resonant magnetic perturbations are used to control the pedestal transport and stability in low electron collisionality (νe*), ITER [ITER Physics Basis Editors et al., Nucl. Fusion 39, 2137 (1999)] relevant, poloidally diverted plasmas. The applied perturbations reduce the height of the density pedestal and increase its width while increasing the height of the electron pedestal temperature and its gradient. The effect of the perturbations on the pedestal gradients is controlled by the current in the perturbation coil, the poloidal mode spectrum of the coil, the neutral beam heating power, and the divertor deuterium fueling rate. Large pedestal instabilities, referred to as edge localized modes (ELMs), are completely eliminated with radial magnetic perturbations (δbr(m∕n)) at the q=m∕n=11∕3 surface exceeding δbr(11∕3)Bϕ−1=2.6×10−4, where Bϕ is the toroidal magnetic field on axis. The resulting ELM-free H-mode plasmas have stationary densities and radiated power, are maintained in DIII-D for up t...


Physics of Plasmas | 2010

Plasma transport in stochastic magnetic field caused by vacuum resonant magnetic perturbations at diverted tokamak edge

G. Park; Choong-Seock Chang; I. Joseph; R.A. Moyer

A kinetic transport simulation for the first 4 ms of the vacuum resonant magnetic perturbations (RMPs) application has been performed for the first time in realistic diverted DIII-D tokamak geometry [J. Luxon, Nucl. Fusion 42, 614 (2002)], with the self-consistent evaluation of the radial electric field and the plasma rotation. It is found that, due to the kinetic effects, the stochastic parallel thermal transport is significantly reduced when compared to the standard analytic model [A. B. Rechester and M. N. Rosenbluth, Phys. Rev. Lett. 40, 38 (1978)] and the nonaxisymmetric perpendicular radial particle transport is significantly enhanced from the axisymmetric level. These trends agree with recent experimental result trends [T. E. Evans, R. A. Moyer, K. H. Burrell et al., Nat. Phys. 2, 419 (2006)]. It is also found, as a side product, that an artificial local reduction of the vacuum RMP fields in the vicinity of the magnetic separatrix can bring the kinetic simulation results to a more detailed agreement with experimental plasma profiles.


Nuclear Fusion | 2008

RMP enhanced transport and rotational screening in simulations of DIII-D plasmas

V.A. Izzo; I. Joseph

Nonlinear magnetohydrodynamic simulations of an equilibrium in the DIII-D geometry with applied resonant magnetic perturbations (RMPs) are performed. The reduction in pedestal density observed in RMP experiments is explained in terms of E × B convection cells crossing the separatrix. Results are obtained both in the absence of plasma rotation and for two rotation profiles having different values at the separatrix. The effects of rotation on RMP screening as well as on the density transport mechanism are obtained from the simulations. Poloidal mode spectra from the simulations show amplification of the resonant components of the error field for the non-rotating plasma. With rotation, this amplification is reduced and a toroidal phase shift appears. At the highest value of rotation, an oscillation in the toroidal mode number n = 3 is observed. These results are considered in light of analytic error field theory.


Journal of Nuclear Materials | 2007

Experimental and numerical studies of separatrix splitting and magnetic footprints in DIII-D

T.E. Evans; I. Joseph; R.A. Moyer; M.E. Fenstermacher; C.J. Lasnier; L.W. Yan


Journal of Nuclear Materials | 2009

Particle, heat, and sheath power transmission factor profiles during ELM suppression experiments on DIII-D

J. G. Watkins; T.E. Evans; M. Jakubowski; R.A. Moyer; O. Schmitz; A. Wingen; M. E. Fenstermacher; I. Joseph; C. J. Lasnier; D.L. Rudakov


Journal of Nuclear Materials | 2007

PEDESTAL, SOL AND DIVERTOR PLASMA PROPERTIES IN DIII-D RMP ELM-SUPPRESSED DISCHARGES AT ITER-RELEVANT EDGE COLLISIONALITY

M.E. Fenstermacher; T.E. Evans; R.A. Moyer; G.D. Porter; J.A. Boedo; K.H. Burrell; M. Groth; I. Joseph; T.H. Osborne; J.G. Watkins

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R.A. Moyer

University of California

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O. Schmitz

University of Wisconsin-Madison

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T.H. Osborne

University of California

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M.E. Fenstermacher

Lawrence Livermore National Laboratory

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C.J. Lasnier

Lawrence Livermore National Laboratory

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P. Gohil

University of California

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