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Dive into the research topics where N. Pablant is active.

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Featured researches published by N. Pablant.


Physics of Plasmas | 2012

Measurements of the deuterium ion toroidal rotation in the DIII-D tokamak and comparison to neoclassical theorya)

B.A. Grierson; K.H. Burrell; W.W. Heidbrink; M.J. Lanctot; N. Pablant; W.M. Solomon

Bulk ion toroidal rotation plays a critical role in controlling microturbulence and MHD stability as well as yielding important insight into angular momentum transport and the investigation of intrinsic rotation. So far, our understanding of bulk plasma flow in hydrogenic plasmas has been inferred from impurity ion velocity measurements and neoclassical theoretical calculations. However, the validity of these inferences has not been tested rigorously through direct measurement of the main-ion rotation in deuterium plasmas, particularly in regions of the plasma with steep pressure gradients where very large differences can be expected between bulk ion and impurity rotation. New advances in the analysis of wavelength-resolved Dα emission on the DIII-D tokamak [J. L. Luxon et al., Fusion Sci. Technol. 48, 807 (2002)] have enabled accurate measurements of the main-ion (deuteron) temperature and toroidal rotation. The Dα emission spectrum is accurately fit using a model that incorporates thermal deuterium char...


Review of Scientific Instruments | 2012

X-ray imaging crystal spectroscopy for use in plasma transport research

Matthew Reinke; Y. Podpaly; M. Bitter; Ian H. Hutchinson; J. E. Rice; L. Delgado-Aparicio; C. Gao; M. Greenwald; K. W. Hill; N.T. Howard; A. Hubbard; J.W. Hughes; N. Pablant; A.E. White; S. M. Wolfe

This research describes advancements in the spectral analysis and error propagation techniques associated with x-ray imaging crystal spectroscopy (XICS) that have enabled this diagnostic to be used to accurately constrain particle, momentum, and heat transport studies in a tokamak for the first time. Doppler tomography techniques have been extended to include propagation of statistical uncertainty due to photon noise, the effect of non-uniform instrumental broadening as well as flux surface variations in impurity density. These methods have been deployed as a suite of modeling and analysis tools, written in interactive data language (IDL) and designed for general use on tokamaks. Its application to the Alcator C-Mod XICS is discussed, along with novel spectral and spatial calibration techniques. Example ion temperature and radial electric field profiles from recent I-mode plasmas are shown, and the impact of poloidally asymmetric impurity density and natural line broadening is discussed in the context of the planned ITER x-ray crystal spectrometer.


Review of Scientific Instruments | 2012

Layout and results from the initial operation of the high-resolution x-ray imaging crystal spectrometer on the Large Helical Device

N. Pablant; M. Bitter; L. Delgado-Aparicio; Motoshi Goto; K. W. Hill; S. Lazerson; Shigeru Morita; A.L. Roquemore; D.A. Gates; Donald Monticello; H. Nielson; A. Reiman; M. Reinke; J. E. Rice; H. Yamada

First results of ion and electron temperature profile measurements from the x-ray imaging crystal spectrometer (XICS) diagnostic on the Large Helical Device (LHD) are presented. This diagnostic system has been operational since the beginning of the 2011 LHD experimental campaign and is the first application of the XICS diagnostic technique to helical plasma geometry. The XICS diagnostic provides measurements of ion and electron temperature profiles in LHD with a spatial resolution of 2 cm and a maximum time resolution of 5 ms (typically 20 ms). Ion temperature profiles from the XICS diagnostic are possible under conditions where charge exchange recombination spectroscopy (CXRS) is not possible (high density) or is perturbative to the plasma (low density or radio frequency heated plasmas). Measurements are made by using a spherically bent crystal to provide a spectrally resolved 1D image of the plasma from line integrated emission of helium-like Ar(16 +). The final hardware design and configuration are detailed along with the calibration procedures. Line-integrated ion and electron temperature measurements are presented, and the measurement accuracy is discussed. Finally central temperature measurements from the XICS system are compared to measurements from the Thomson scattering and CXRS systems, showing excellent agreement.


Plasma Physics and Controlled Fusion | 2017

Performance and properties of the first plasmas of Wendelstein 7-X

T. Klinger; A. Alonso; S. Bozhenkov; R. Burhenn; A. Dinklage; G. Fuchert; J. Geiger; O. Grulke; A. Langenberg; M. Hirsch; G. Kocsis; J. Knauer; A. Krämer-Flecken; H. P. Laqua; Samuel A. Lazerson; Matt Landreman; H. Maaßberg; S. Marsen; M. Otte; N. Pablant; E. Pasch; K. Rahbarnia; T. Stange; T. Szepesi; H. Thomsen; P. Traverso; J. L. Velasco; T. Wauters; G. Weir; T. Windisch

The optimized, superconducting stellarator Wendelstein 7-X went into operation and delivered first measurement data after 15 years of construction and one year commissioning. Errors in the magnet assembly were confirmend to be small. Plasma operation was started with 5 MW electron cyclotron resonance heating (ECRH) power and five inboard limiters. Core plasma values of keV, keV at line-integrated densities were achieved, exceeding the original expectations by about a factor of two. Indications for a core-electron-root were found. The energy confinement times are in line with the international stellarator scaling, despite unfavourable wall conditions, i.e. large areas of metal surfaces and particle sources from the limiter close to the plasma volume. Well controlled shorter hydrogen discharges at higher power (4 MW ECRH power for 1 s) and longer discharges at lower power (0.7 MW ECRH power for 6 s) could be routinely established after proper wall conditioning. The fairly large set of diagnostic systems running in the end of the 10 weeks operation campaign provided first insights into expected and unexpected physics of optimized stellarators.


Nuclear Fusion | 2013

Inter-machine validation study of neoclassical transport modelling in medium- to high-density Stellarator-Heliotron plasmas

A. Dinklage; M. Yokoyama; K. Tanaka; J.L. Velasco; D. Lopez-Bruna; C. D. Beidler; S. Satake; E. Ascasibar; J. Arevalo; J. Baldzuhn; Y. Feng; D.A. Gates; J. Geiger; K. Ida; M. Isaev; M. Jakubowski; A. Lopez-Fraguas; H. Maaßberg; J. Miyazawa; T. Morisaki; S. Murakami; N. Pablant; S. Kobayashi; R. Seki; C. Suzuki; Y. Suzuki; Yu. Turkin; A. Wakasa; R. Wolf; H. Yamada

A comparative study of energy transport for medium- to high-density discharges in the stellarator-heliotrons TJ-II, W7-AS and LHD is carried out. The specific discharge parameters are chosen to apply a recently concluded benchmarking study of neoclassical (NC) transport coefficients (Beidler et al 2011 Nucl. Fusion 51 076001) to perform this validation study. In contrast to previous experiments at low densities for which electron transport was predominant (Yokoyama et al 2007 Nucl. Fusion 47 1213), the current discharges also exhibit significant ion energy transport. As it affects the energy transport in 3D devices, the ambipolar radial electric field is addressed as well. For the discharges described, ion-root conditions, i.e. a small negative radial electric field were found. The energy transport in the peripheral region cannot be explained by NC theory. Within a core region(r/a < 1/2 ~ 2/3), the predicted NC energy fluxes comply with experimental findings for W7-AS. For TJ-II, compliance in the core region is found for the particle transport and the electron energy transport. For the specific LHD discharges, the core energy transport complied with NC theory except for the electron energy transport in the inward-shifted magnetic configuration. The NC radial electric field tends to agree with experimental results for all devices but is measured to be more negative in the core of both LHD and TJ-II. As a general observation, the energy confinement time approaches the gyro-Bohm-type confinement scaling ISS04 (Yamada et al 2005 Nucl. Fusion 45 1684). This work is carried out within the International Stellarator-Heliotron Profile Database (www.ipp.mpg.de/ISS and http://ishpdb.nifs.ac.jp/index.html).


Nuclear Fusion | 2013

On the formation and stability of long-lived impurity-ion snakes in Alcator C-Mod

L. Delgado-Aparicio; L. Sugiyama; R. Granetz; D.A. Gates; J. E. Rice; M.L. Reinke; W. Bergerson; M. Bitter; D. L. Brower; E.D. Fredrickson; C. Gao; M. Greenwald; K. W. Hill; A. Hubbard; J. Irby; J.W. Hughes; E. Marmar; N. Pablant; S. Scott; R. Wilson; S. M. Wolfe; S.J. Wukitch

Long-lived (1, 1) ?snake? modes were discovered nearly three decades ago, but basic questions regarding their formation, stability, and superb particle confinement?shown by surviving tens to hundreds of sawtooth cycles?have remained unanswered. High-resolution spectroscopic imaging diagnostics permit studies of heavy-impurity-ion snakes with unprecedented temporal and spatial resolution, making it possible to positively identify the SXR signals with specific ion charge states and to infer, for the first time, the perturbed impurity density, Zeff, and resistivity at the centre of these long-lived helical modes. The results show a new scenario for the formation of heavy-impurity-ion snakes, which can begin as a broad 1/1 kink asymmetry of the central impurity-ion density, that grows and undergoes a seamless transition to a large crescent-shaped helical island-like structure inside q?<?1, with a regularly sawtoothing core. This type of formation departs strongly from the nonlinear island model based on a modified Rutherford equation proposed originally to describe the pellet-induced snakes and expanded further to account for the impurity effects (e.g. and ). These new high-resolution observations show details of their evolution and the accompanying sawtooth oscillations that suggest important differences between the density and temperature dynamics, ruling out a purely pressure-driven process. Instead, many features arise naturally from nonlinear interactions in a 3D MHD model that separately evolves the plasma density and temperature.


Review of Scientific Instruments | 2014

Upgrades of imaging x-ray crystal spectrometers for high-resolution and high-temperature plasma diagnostics on EAST

B. Lyu; F. D. Wang; X. Y. Pan; J.L. Chen; Jia Fu; Yingying Li; M. Bitter; K. W. Hill; L. F. Delgado-Aparicio; N. Pablant; S. G. Lee; Y. J. Shi; Minyou Ye; Baonian Wan

Upgrade of the imaging X-ray crystal spectrometers continues in order to fulfill the high-performance diagnostics requirements on EAST. For the tangential spectrometer, a new large pixelated two-dimensional detector was deployed on tokamaks for time-resolved X-ray imaging. This vacuum-compatible detector has an area of 83.8 × 325.3 mm(2), a framing rate over 150 Hz, and water-cooling capability for long-pulse discharges. To effectively extend the temperature limit, a double-crystal assembly was designed to replace the previous single crystals for He-like argon line measurement. The tangential spectrometer employed two crystal slices attached to a common substrate and part of He- and H-like Ar spectra could be recorded on the same detector when crystals were chosen to have similar Bragg angles. This setup cannot only extend the measurable Te up to 10 keV in the core region, but also extend the spatial coverage since He-like argon ions will be present in the outer plasma region. Similarly, crystal slices for He-like iron and argon spectra were adopted on the poloidal spectrometer. Wavelength calibration for absolute rotation velocity measurement will be studied using cadmium characteristic L-shell X-ray lines excited by plasma radiation. A Cd foil is placed before the crystal and can be inserted and retracted for in situ wavelength calibration. The Geant4 code was used to estimate X-ray fluorescence yield and optimize the thickness of the foil.


Physics of Plasmas | 2014

Quasilinear Carbon Transport In An Impurity Hole Plasma In LHD

D.R. Mikkelsen; K. Tanaka; Masanori Nunami; T.-H. Watanabe; H. Sugama; M. Yoshinuma; K. Ida; Yasuhiro Suzuki; M. Goto; S. Morita; B. Wieland; I. Yamada; Ryo Yasuhara; T. Tokuzawa; T. Akiyama; N. Pablant

Comprehensive electrostatic gyrokinetic linear stability calculations for ion-scale microinstabilities in an LHD plasma with an ion-internal transport barrier (ITB) and carbon “impurity hole” are used to make quasilinear estimates of particle flux to explore whether microturbulence can explain the observed outward carbon fluxes that flow “up” the impurity density gradient. The ion temperature is not stationary in the ion-ITB phase of the simulated discharge, during which the core carbon density decreases continuously. To fully sample these varying conditions, the calculations are carried out at three radial locations and four times. The plasma parameter inputs are based on experimentally measured profiles of electron and ion temperature, as well as electron and carbon density. The spectroscopic line-average ratio of hydrogen and helium densities is used to set the density of these species. Three ion species (H,He,C) and the electrons are treated kinetically, including collisions. Electron instability driv...


Nuclear Fusion | 2015

Integrated discharge scenario for high-temperature helical plasma in LHD

K. Nagaoka; H. Takahashi; S. Murakami; H. Nakano; Y. Takeiri; H. Tsuchiya; M. Osakabe; K. Ida; M. Yokoyama; M. Yoshinuma; S. Morita; M. Goto; T. Oishi; N. Pablant; Keisuke Fujii; K. Tanaka; Noriko Tamura; Y. Nakamura; X. Du; T. Ido; A. Shimizu; S. Kubo; H. Igami; R. Seki; C. Suzuki; Y. Suzuki; K. Tsumori; K. Ikeda; M. Kisaki; Y. Yoshimura

The discharge scenario of high temperature plasma with a helical configuration has significantly progressed. The increase of central ion temperature due to the reduction of wall recycling was clearly observed. The peaking of the ion heating profile and the reduction of charge exchange loss of energetic ions play an important role for further improvement of ion heat transport in the ion internal transport barrier (ITB) core. The ion ITB and electron ITB have been successfully integrated due to the superposition of centrally focused electron cyclotron heating to the ion ITB plasma, and the high temperature regime of the ion temperature comparable to the electron temperature (Ti ~ Te) has been significantly extended. The width of the ion ITB formed with electron ITB is wider than the width of electron ITB. The positive radial electric field was observed in the integrated ITB plasma by a heavy ion beam probe, while the negative radial electric field was observed in ion ITB plasmas. The ion temperature gradient decreases with the increase of the temperature ratio (Te /Ti).


Review of Scientific Instruments | 2016

Measurement of deuterium density profiles in the H-mode steep gradient region using charge exchange recombination spectroscopy on DIII-D

S.R. Haskey; B.A. Grierson; K.H. Burrell; C. Chrystal; R. J. Groebner; D. H. Kaplan; N. Pablant; L. Stagner

Recent completion of a thirty two channel main-ion (deuterium) charge exchange recombination spectroscopy (CER) diagnostic on the DIII-D tokamak [J. L. Luxon, Nucl. Fusion 42, 614 (2002)] enables detailed comparisons between impurity and main-ion temperature, density, and toroidal rotation. In a H-mode DIII-D discharge, these new measurement capabilities are used to provide the deuterium density profile, demonstrate the importance of profile alignment between Thomson scattering and CER diagnostics, and aid in determining the electron temperature at the separatrix. Sixteen sightlines cover the core of the plasma and another sixteen are densely packed towards the plasma edge, providing high resolution measurements across the pedestal and steep gradient region in H-mode plasmas. Extracting useful physical quantities such as deuterium density is challenging due to multiple photoemission processes. These challenges are overcome using a detailed fitting model and by forward modeling the photoemission using the FIDASIM code, which implements a comprehensive collisional radiative model.

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M. Bitter

Princeton Plasma Physics Laboratory

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L. Delgado-Aparicio

Massachusetts Institute of Technology

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Philip C. Efthimion

Princeton Plasma Physics Laboratory

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