I. Joseph
University of California, San Diego
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Featured researches published by I. Joseph.
Nuclear Fusion | 2008
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
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
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
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
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
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
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
T.E. Evans; I. Joseph; R.A. Moyer; M.E. Fenstermacher; C.J. Lasnier; L.W. Yan
Journal of Nuclear Materials | 2009
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
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